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OPERATING DATA REPORT                                                     ,
OPERATING DATA REPORT DOCKET NO. _050-0298 DATE 10-2-86 COMPLETED BY J. E. Thompson TELEPHONE (402)825-3811 OPERATING STATUS
DOCKET NO. _050-0298 DATE   10-2-86 COMPLETED BY     J. E. Thompson TELEPHONE (402)825-3811 OPERATING STATUS Cooper Nuclear Station                            Notes
: l. Unit Name:
: l. Unit Name:
: 2. Reporting Period:       September, 1986                                                                                     ,
Cooper Nuclear Station Notes
: 3. Licensed Thermal Power (MWt):       2381
: 2. Reporting Period:
: 4. Nameplate Rating (Gross MWe):         836
September, 1986
: 5. Design Electrical Rating (Net MWe):     778
: 3. Licensed Thermal Power (MWt):
: 6. Maximum Dependable Capacity (Gross MWe):         787
2381
: 7. Maximum Dependable Capacity (Net MWe):           764
: 4. Nameplate Rating (Gross MWe):
836
: 5. Design Electrical Rating (Net MWe):
778
: 6. Maximum Dependable Capacity (Gross MWe):
787
: 7. Maximum Dependable Capacity (Net MWe):
764
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
: 9. Power Level To Which Restricted,1f Any (Net MWe):
: 9. Power Level To Which Restricted,1f Any (Net MWe):
: 10. Reasons For Restrictions.If Any:
: 10. Reasons For Restrictions.If Any:
i This Month             Yr.-to Date         Cumulative
i This Month Yr.-to Date Cumulative
: 11. Ilours in Reporting Period                                 720.0               6,551.0           107.400.0
: 11. Ilours in Reporting Period 720.0 6,551.0 107.400.0
: 12. Number Of flours Reactor Was Critical                     720.0               6.492.I             81.505.2
: 12. Number Of flours Reactor Was Critical 720.0 6.492.I 81.505.2
: 13. Reactor Resene Shutdown llours                               0.0                     0.0                 0.0 I4. Ilours Generator On Line                                   720.0               6,468.2             80,174.0
: 13. Reactor Resene Shutdown llours 0.0 0.0 0.0 I4. Ilours Generator On Line 720.0 6,468.2 80,174.0
: 15. Unit Reserve Shutdown flours                                 0.0                     0.0                 0.0
: 15. Unit Reserve Shutdown flours 0.0 0.0 0.0
: 16. Gross Thermal Energy Generated (MWil)             1,108.200.0           12.483.195.0         157.345.861.0
: 16. Gross Thermal Energy Generated (MWil) 1,108.200.0 12.483.195.0 157.345.861.0
: 17. Gross Electrical Energy Generated (MWil)             366,361.0         4,164,538.0         50,304,511.0
: 17. Gross Electrical Energy Generated (MWil) 366,361.0 4,164,538.0 50,304,511.0
: 18. Net Electrical Energy Generated (MWill               3S3,632.0         4,013,097.0         48,467,457.0
: 18. Net Electrical Energy Generated (MWill 3S3,632.0 4,013,097.0 48,467,457.0
: 19. Unit Service Factor                                         100.0                   98.7                 74.6
: 19. Unit Service Factor 100.0 98.7 74.6
: 20. Unit Availability Factor                                   100.0                   98.7                 74.6
: 20. Unit Availability Factor 100.0 98.7 74.6
: 21. Unit Capacity Factor (Using Mi>C Net,                       64.3                   80.2                 59.I
: 21. Unit Capacity Factor (Using Mi>C Net, 64.3 80.2 59.I
: 22. Unit Capacity Factor (Using DER Net)                         63.1                   78.7                 58.0
: 22. Unit Capacity Factor (Using DER Net) 63.1 78.7 58.0
: 23. Unit Forced Outage Rate                                       0.0                     1.3                 4.7
: 23. Unit Forced Outage Rate 0.0 1.3 4.7
: 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each):
: 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each):
1986 Refueling and Maintenance Outage starting October 4, 1986 with an approximate duration of 10 weeks.
1986 Refueling and Maintenance Outage starting October 4, 1986 with an approximate duration of 10 weeks.
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
: 26. Units in Test Status (Prior to Commercial Operation):                       Forecast             Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY CO\lM ERCI \L OPER ATION 8701060171 860930 DR     ADOCK 0500           8                                                 g        p,j773
: 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY CO\\lM ERCI \\L OPER ATION 8701060171 860930 g
p,j773 DR ADOCK 0500 8


[                                                                                                                                             . -: -
[
'E                                                                                                                                                     .
'E s
s                                                                                                  ,                        .
DOCKET NO.
UNIT SHUTDOWNS AND POWER REDUCTIONS                     DOCKET NO.          50-298 UNIT NAME CNS                             .
50-298 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME CNS DATE 10-2-86 REPORT MONTH September. 1986 COMPLETED BY ~
DATE     10-2-86           .
J.
REPORT MONTH September. 1986                 COMPLETED BY ~ J. E. Thompson
E. Thompson TELEPHONE (402)825-3811 3?
''                                                                                                          TELEPHONE           (402)825-3811         - '
3
                        -,      3?        3g      .Y     ' Licensee     5 r,       !*.                Cause & Corrective No.         Date   g       3g             ,g g 5       Event       u '9       83                       Action to H
.Y
                                  $5         5   3 di c     Report #       <# G       gu                 Prevent Recurrence
' Licensee 5 r, Cause & Corrective No.
                                                        @                              u O
Date g
86-06                 F       0         H       4         N/A         N/A         N/A   An excessive unidentified leak rate in the drywell initiated a 24 hour LC0~as required by Technical Specifi-cations. Power was reduced to allow entry into the,drywell to invest!igate the problem. The source of the Icak was identified as the packing on the "A" Reactor Recirculation pump dis-charge valve. After the valve pack-ing was adjusted and.successfully tested, normal plant operation re-sumed. The valve packing will be replaced during the next extended outage.
3g g
I                   2                                                 3                             4 F: Forced         Reason:                                           Method:                         Exhibit G-Instructions S: Scheduled       A-Equipment Failure (Explain)                       1-Manual                       for Preparation of Data B-Maintenance of Test                             2-Manual Scram.                 Entry Sheets for Licensee C-Refueling                                       3-Automatic Scram.               Event Report (LER) File (NUREG-D-Regulatory Restriction                           441her (Explain)                 0161)
,g g 5 Event u '9 83 Action to
E Operator Training & Ucense Examination F-Administrative                                                               5
$5 5
                                                                        ~
3 di c Report #
G-Operational Error (Explain)                                           '
<# G gu Prevent Recurrence H
Exhibit I- Same Source (9/77)               Il-Other (Explain)                         -
u O
E   e-
86-06 F
0 H
4 N/A N/A N/A An excessive unidentified leak rate in the drywell initiated a 24 hour LC0~as required by Technical Specifi-cations.
Power was reduced to allow entry into the,drywell to invest!igate the problem. The source of the Icak was identified as the packing on the "A" Reactor Recirculation pump dis-charge valve. After the valve pack-ing was adjusted and.successfully tested, normal plant operation re-sumed. The valve packing will be replaced during the next extended outage.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 441her (Explain) 0161)
E Operator Training & Ucense Examination F-Administrative 5
G-Operational Error (Explain)
~
Exhibit I-Same Source (9/77)
Il-Other (Explain)
E e-


Operations Narrative Cooper Nuclear Station September 1986
Operations Narrative Cooper Nuclear Station September 1986
                -The plant' operated the month of September with no scheduled or unscheduled'   '
-The plant' operated the month of September with no scheduled or unscheduled' shutdowns, and one unscheduled power reduction. A capacity factor of 64.3%
shutdowns, and one unscheduled power reduction. A capacity factor of 64.3%
was achieved for'the month.
was achieved for'the month.
                -On September 21, a high unidentified drywell: leak rate put the plant into a 24 hour limiting condition for operation.. Power was reduced to less than 18%
-On September 21, a high unidentified drywell: leak rate put the plant into a 24 hour limiting condition for operation.. Power was reduced to less than 18%
                . thermal to gain access to the drywell. The leakage source was found to be the discharge valve for reactor recirculation. loop "A". The valve packing was adjusted to reduce the leak rate to an acceptable level. After succeasful valve testing, normal operation resumed.
. thermal to gain access to the drywell. The leakage source was found to be the discharge valve for reactor recirculation. loop "A".
The valve packing was adjusted to reduce the leak rate to an acceptable level. After succeasful valve testing, normal operation resumed.
1 i
1 i


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Ql c ~.;.m..a -
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AVERAGE DAILY UNIT POWER LEVEL j
AVERAGE DAILY UNIT POWER LEVEL                                                                     j
.<s 4
                                                                                                                                                                        .<s 4
DOCKET NO.
DOCKET NO.       50-0298                             .m t Gl.           '
50-0298
UNIT     CNS DATE     10-2-86                               q1
.m t Gl.
                                                                                                                                                                        . c{
UNIT CNS DATE 10-2-86 q1
                                                                  'T                                         COMPLETED BY           J. E. Thompson                         7,y TELEPHONE         (402)825-3811                   ,
. c{
                                                                                                                                                                          ;-}
'T COMPLETED BY J. E. Thompson 7,y
4
;-}
::5 MON 1H           September, 1986 3.j i                   -
TELEPHONE (402)825-3811 4
a DAY           AVERAGE DAILY POWER LEVEL                         DAY                                                                           "
::5 MON 1H September, 1986 3.j i
AVERAGE DAILY POWER LEVEL (MWe-Net)                                             (MWe-Net)                                                     '1 r ~
a DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
449 l
(MWe-Net)
519 17                 523
'1 r ~
[    .
l 449
2        _                                                    18                 522                                                             C o~
[
                            '3                         517                                 19                 523 4                         520                                 20                 454                                 -
17 523 2
5                          518                                                    342 21                                                                          .,3 6                         518                                                     319 22                                                                              --i
519 18 522 C
                      ~
o
7                         452                                  23                 521 i) 8                         519                                 24                 521                                                         i:
'3 517 19 523
                              -9                         519                                                     520 25 10                         519                                 26                 520                                                       7, g
~
11                         520                                 27                 453                                                     , f ,;
4 520 20 454 518
:e 12'                         519                                                   447                                                         11 .
.,3 5
28                                                                  ..
21 342 6
449                                                                                                    ,s - y 13                                                             29                 521                                           f i 34                         456                                                     518                                                               '
518 22 319
30
--i
                          -15                           519                                 3g 16                         524
~
                                                                                                                                                                    ,l   {' f INSTRUCTIONS
452 7
;                          On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to                               . i.
23 521 i) 8 519 24 521 i:
-9 519 25 520 10 519 26 520 7,g 11 520 27 453
, f,;
:e 12' 519 28 447 11.
..,s - y 13 449 29 521 f i 34 456 30 518
-15 519 3g 16 524
,l
{' f INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to
. i.
the nea est whole megawatt.
the nea est whole megawatt.
4! .
4!
(9/77)                         ,,
(9/77) a s
a s   %
w a
w a
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  . ,; = .
COOPER NUCLEAR STATION
COOPER NUCLEAR STATION
:i:       Nebraska Public Power District               ''- " * ?gg ,*>"??M;";,*"^1"   ^ " ' ' '
:i:
CNSS867754 October 2, 1986 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Nebraska Public Power District
''- " * ?gg,*>"??M;";,*"^1
" ^ " ' ' '
CNSS867754 October 2, 1986 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C.
20555


==Subject:==
==Subject:==
Line 124: Line 160:
Enclosed for your information and use is the Cooper Nuclear Station Monthly Operating Status Report for September, 1986. The report includes Operating Status, Average Daily Unit Power Level Unit Shutdown Data, and a Narrative Summary of Operating Experience.
Enclosed for your information and use is the Cooper Nuclear Station Monthly Operating Status Report for September, 1986. The report includes Operating Status, Average Daily Unit Power Level Unit Shutdown Data, and a Narrative Summary of Operating Experience.
Should you have any comments or require additional information regarding this report, please contact me.
Should you have any comments or require additional information regarding this report, please contact me.
Sincerely, t   W
Sincerely, t
            . Horn Di     on Manager of Nuclear 6perations GRH:drf Enclosure cc: G. D. Watson w/ enc.
W Horn Di on Manager of Nuclear 6perations GRH:drf Enclosure cc:
G. D. Watson w/ enc.
A. C. Gehr w/ enc.
A. C. Gehr w/ enc.
R. D. Martin w/ enc.
R. D. Martin w/ enc.
Y')$,}}}
Y')$,}}}

Latest revision as of 21:36, 6 December 2024

Monthly Operating Rept for Sept 1986
ML20207F653
Person / Time
Site: Cooper Entergy icon.png
Issue date: 09/30/1986
From: Horn G, Jacqueline Thompson
NEBRASKA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
CNSS867754, NUDOCS 8701060171
Download: ML20207F653 (5)
v • d • e


Text

.

OPERATING DATA REPORT DOCKET NO. _050-0298 DATE 10-2-86 COMPLETED BY J. E. Thompson TELEPHONE (402)825-3811 OPERATING STATUS

l. Unit Name:

Cooper Nuclear Station Notes

2. Reporting Period:

September, 1986

3. Licensed Thermal Power (MWt):

2381

4. Nameplate Rating (Gross MWe):

836

5. Design Electrical Rating (Net MWe):

778

6. Maximum Dependable Capacity (Gross MWe):

787

7. Maximum Dependable Capacity (Net MWe):

764

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
9. Power Level To Which Restricted,1f Any (Net MWe):
10. Reasons For Restrictions.If Any:

i This Month Yr.-to Date Cumulative

11. Ilours in Reporting Period 720.0 6,551.0 107.400.0
12. Number Of flours Reactor Was Critical 720.0 6.492.I 81.505.2
13. Reactor Resene Shutdown llours 0.0 0.0 0.0 I4. Ilours Generator On Line 720.0 6,468.2 80,174.0
15. Unit Reserve Shutdown flours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWil) 1,108.200.0 12.483.195.0 157.345.861.0
17. Gross Electrical Energy Generated (MWil) 366,361.0 4,164,538.0 50,304,511.0
18. Net Electrical Energy Generated (MWill 3S3,632.0 4,013,097.0 48,467,457.0
19. Unit Service Factor 100.0 98.7 74.6
20. Unit Availability Factor 100.0 98.7 74.6
21. Unit Capacity Factor (Using Mi>C Net, 64.3 80.2 59.I
22. Unit Capacity Factor (Using DER Net) 63.1 78.7 58.0
23. Unit Forced Outage Rate 0.0 1.3 4.7
24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each):

1986 Refueling and Maintenance Outage starting October 4, 1986 with an approximate duration of 10 weeks.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY CO\\lM ERCI \\L OPER ATION 8701060171 860930 g

p,j773 DR ADOCK 0500 8

[

'E s

DOCKET NO.

50-298 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME CNS DATE 10-2-86 REPORT MONTH September. 1986 COMPLETED BY ~

J.

E. Thompson TELEPHONE (402)825-3811 3?

3

.Y

' Licensee 5 r, Cause & Corrective No.

Date g

3g g

,g g 5 Event u '9 83 Action to

$5 5

3 di c Report #

<# G gu Prevent Recurrence H

u O

86-06 F

0 H

4 N/A N/A N/A An excessive unidentified leak rate in the drywell initiated a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LC0~as required by Technical Specifi-cations.

Power was reduced to allow entry into the,drywell to invest!igate the problem. The source of the Icak was identified as the packing on the "A" Reactor Recirculation pump dis-charge valve. After the valve pack-ing was adjusted and.successfully tested, normal plant operation re-sumed. The valve packing will be replaced during the next extended outage.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 441her (Explain) 0161)

E Operator Training & Ucense Examination F-Administrative 5

G-Operational Error (Explain)

~

Exhibit I-Same Source (9/77)

Il-Other (Explain)

E e-

Operations Narrative Cooper Nuclear Station September 1986

-The plant' operated the month of September with no scheduled or unscheduled' shutdowns, and one unscheduled power reduction. A capacity factor of 64.3%

was achieved for'the month.

-On September 21, a high unidentified drywell: leak rate put the plant into a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limiting condition for operation.. Power was reduced to less than 18%

. thermal to gain access to the drywell. The leakage source was found to be the discharge valve for reactor recirculation. loop "A".

The valve packing was adjusted to reduce the leak rate to an acceptable level. After succeasful valve testing, normal operation resumed.

1 i

j;!.,.,

Ql c ~.;.m..a -

AVERAGE DAILY UNIT POWER LEVEL j

."??M;";,*"^1

" ^ " ' ' '

CNSS867754 October 2, 1986 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Monthly Operation Status Report for September, 1986 Docket No. 50-298 Gentlemen:

Enclosed for your information and use is the Cooper Nuclear Station Monthly Operating Status Report for September, 1986. The report includes Operating Status, Average Daily Unit Power Level Unit Shutdown Data, and a Narrative Summary of Operating Experience.

Should you have any comments or require additional information regarding this report, please contact me.

Sincerely, t

W Horn Di on Manager of Nuclear 6perations GRH:drf Enclosure cc:

G. D. Watson w/ enc.

A. C. Gehr w/ enc.

R. D. Martin w/ enc.

Y')$,}

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