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| number = ML17332A879
| number = ML17332A879
| issue date = 07/31/1995
| issue date = 07/31/1995
| title = Monthly Operating Rept for Jul 1995 for DC Cook Nuclear Plant Unit 1.W/950808 Ltr
| title = Monthly Operating Rept for Jul 1995 for DC Cook Nuclear Plant Unit 1
| author name = Blind A, Turner D
| author name = Blind A, Turner D
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
| author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
Line 18: Line 18:
{{#Wiki_filter:PRIORITY (ACCELERATED RZDS PROCESSZNG)
{{#Wiki_filter:PRIORITY (ACCELERATED RZDS PROCESSZNG)
REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)
REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)
ACCESSION NBR:9508150067         DOC.DATE:   95/07/31 NOTARIZED: NO               DOCKET FACIL:50-315 Donald C. Cook     Nuclear   Power   Plant,   Unit 1, Indiana   M 05000315 p AUTH. NAME         AUTHOR AFFILIATION TURNER,D.G.         Indiana Michigan Power Co. (formerly Indiana S Michigan Ele BLIND,A.A.         Indiana Michigan Power Co. (formerly Indiana & Michigan, Ele         R RECIP.NAME         RECIPIENT AFFILIATXON
ACCESSION NBR:9508150067 DOC.DATE: 95/07/31 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 p
AUTH.NAME AUTHOR AFFILIATION TURNER,D.G.
Indiana Michigan Power Co. (formerly Indiana S Michigan Ele BLIND,A.A.
Indiana Michigan Power Co.
(formerly Indiana
& Michigan, Ele R
RECIP.NAME RECIPIENT AFFILIATXON


==SUBJECT:==
==SUBJECT:==
Monthly operating rept     for Jul   1995 for   DC Cook Nuclear Plant Unit 1.W/950808     ltr.
Monthly operating rept for Jul 1995 for DC Cook Nuclear Plant Unit 1.W/950808 ltr.
DISTRIBUTION CODE: IE24D       COPIES RECEIVED:LTR         ENCL     SIZE:
DISTRIBUTION CODE:
TITLE: Monthly Operating Report (per Tech Specs NOTES RECIPIENT           COPIES            RECXPIENT          COPIES ID CODE/NAME       LTTR ENCL        ID  CODE/NAME        LTTR ENCL PD3-1 PD               1      1      HICKMAN,J              1    1 INTERNAL: AEOD/SPD/RRAB           1      1                              1    1 NRR/DISP/PIPB           1     1     NRR/DRPM/PECB           1     1 RGN3                    1     1 EXTERNAL: LITCO BRYCE,J H          1     1     NOAC                    1     1 NRC PDR                1      1 D
IE24D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Monthly Operating Report (per Tech Specs NOTES RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/SPD/RRAB NRR/DISP/PIPB RGN3 EXTERNAL: LITCO BRYCE,J H
NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1 RECXPIENT ID CODE/NAME HICKMAN,J NRR/DRPM/PECB NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 D
N NOTE TO ALL "RZDS" RECZPZENTS:
N NOTE TO ALL "RZDS" RECZPZENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D8 (415-2083) TO ELZMZNATE YOUR NAME FROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEED' TOTAL NUMBER OF COPIES REQUIRED: LTTR           10   ENCL     10
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL
: DESK, ROOM OWFN 5D8 (415-2083)
TO ELZMZNATE YOUR NAME FROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEED' TOTAL NUMBER OF COPIES REQUIRED:
LTTR 10 ENCL 10


indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 August 8, 1995 U.S. Nuclear Regulatory Commission ATTN:       Document Control Desk Washington,           D.C. 20555 Gentlemen:
indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 August 8,
Pursuant to the requirements of Donald C. Cook Nuclear Plant Unit 1 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of July 1995     is submitted.
1995 U.S. Nuclear Regulatory Commission ATTN:
Respectfully, A.A. Blind Plant Manager Attachment c:       NRC     Region   III D.R. Hahn R.C. Callen S .       Hamming J.G. Keppler INPO Records Center ANI Nuclear Engineering Department E.E.       Fitzpatrick W.G.     Smith, Jr.
Document Control Desk Washington, D.C.
S.J. Brewer D.W. Paul S.H. Steinhart J.L. Leichner J.A. Isom D.G. Turner E.A. Smarrella M.E. Russo 9508l50067 950731 PDR R
20555 Gentlemen:
ADQCK 050003i5 PDR
Pursuant to the requirements of Donald C.
                                                          ~
Cook Nuclear Plant Unit 1 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of July 1995 is submitted.
                                                              /
Respectfully, A.A. Blind Plant Manager Attachment c:
NRC Region III D.R.
Hahn R.C. Callen S.
Hamming J.G.
Keppler INPO Records Center ANI Nuclear Engineering Department E.E. Fitzpatrick W.G. Smith, Jr.
S.J.
Brewer D.W. Paul S.H. Steinhart J.L. Leichner J.A.
Isom D.G. Turner E.A. Smarrella M.E. Russo 9508l50067 950731 PDR ADQCK 050003i5 R
PDR
~ /


N.R.CD OPERATING DATA REPORT DOCKET NO. 50-315 DATE 02/Aug/95 COMPLETED BY DG Turner TELEPHONE 616-465-5901 OPERATING STATUS
N.R.CD OPERATING DATA REPORT DOCKET NO.
: 1. Unit Name                   D. C. Cook Unit 1
50-315 DATE 02/Aug/95 COMPLETED BY DG Turner TELEPHONE 616-465-5901 OPERATING STATUS
: 2. Reporting Period                           July 1995 notes
: 1. Unit Name D.
: 3. Licensed Thermal Power (MWt)                   3250 4., Name Plate Rating (Gross MWe)                 1152
C.
: 5. Design Electrical Rating (Net MWe)             1020
Cook Unit 1
: 6. Maximum Dependable Capacity (GROSS MWe) 1056
: 2. Reporting Period July 1995 notes
: 7. Maximum Dependable Capacity (Net MWe)           1000
: 3. Licensed Thermal Power (MWt) 3250 4., Name Plate Rating (Gross MWe) 1152
: 8. If Changes Occur in Capacity Ratings (Items no. 3 through 7) Since Last Report Give Reasons
: 5. Design Electrical Rating (Net MWe) 1020 6.
: 9. Power Level To Which     Restricted. If Any (Net   MWe) 10'. Reasons   For Restrictions. If Any:
Maximum Dependable Capacity (GROSS MWe) 1056 7.
This  Mo. Yr. to Date  Cumm.
Maximum Dependable Capacity (Net MWe) 1000
: 11. Hours   in Reporting Period                 744.0      5088.0  180408.0
: 8. If Changes Occur in Capacity Ratings (Items no.
: 12. No. 'of Hrs. Reactor Was Critical           338.0      4682.0  136592.9
3 through
: 13. Reactor Reserve Shutdown Hours                 0.0          0.0    463.0
: 7) Since Last Report Give Reasons 9.
: 14. Hours Generator on Line                     315.4      4659.4  134483.0
Power Level To Which Restricted. If Any (Net MWe) 10'.
: 15. Unit Reserve Shutdown Hours                   0.0          0.0    321.0
Reasons For Restrictions. If Any:
: 16. Gross Therm. Energy Gen. (MWH)             727724    14279008  396399585
: 11. Hours in Reporting Period 12.
: 17. Gross Elect. Energy Gen. (MWH)             226520      4645030 128650470
No. 'of Hrs. Reactor Was Critical
: 18. Net Elect. Energy Gen. (MWH)               215173      4476987 123758302
: 13. Reactor Reserve Shutdown Hours
: 19. Unit Service Factor                         42.4        91.6      75.4
: 14. Hours Generator on Line
: 20. Unit Availability Factor                     42.4        91.6      75.4
: 15. Unit Reserve Shutdown Hours
: 21. Unit Capacity Factor   (MDC Net)           28.9        88.0      68.4
: 16. Gross Therm.
: 22. Unit Capacity Factor   (DER Net)           28.4       '86.3       66.6 23,  Unit  Forced Outage Rate                      57.6         8.4       5.9 24 'hutdowns Scheduled over Next Six Months (Type, Date,and Duration):
Energy Gen.
None
(MWH) 17.
: 25. If Shut  Down At End of Report Se tember 23, 1995 Period, Estimated Date of Startup:
Gross Elect.
: 26. Units    in Test Status (Prior to Commercial Operation):
Energy Gen.
Forecast  Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
(MWH)
: 18. Net Elect.
Energy Gen.
(MWH)
: 19. Unit Service Factor
: 20. Unit Availability Factor
: 21. Unit Capacity Factor (MDC Net)
: 22. Unit Capacity Factor (DER Net) 23, Unit Forced Outage Rate 24 'hutdowns Scheduled over Next Six None This Mo.
Yr. to Date 744.0 5088.0 338.0 4682.0 0.0 0.0 315.4 4659.4 0.0 0.0 727724 14279008 226520 4645030 215173 4476987 42.4 91.6 42.4 91.6 28.9 88.0 28.4
'86.3 57.6 8.4 Months (Type, Date,and Cumm.
180408.0 136592.9 463.0 134483.0 321.0 396399585 128650470 123758302 75.4 75.4 68.4 66.6


0 AVERAGE DAILY POWER LEVEL  (MWe-Net)
===5.9 Duration)===
DOCKET NO.        50-315 UNIT                  ONE  .
: 25. If Shut Down At End of Report Period, Estimated Date of Startup:
DATE          02/Aug/95 COMPLETED BY  DG Turner TELEPHONE  616-465-5901 MONTH        July 1995 AVERAGE DAILY                        AVERAGE DAILY DAY      POWER LEVEL            DAY          POWER LEVEL 95/07/01        545            95/07/17                0 95/07/02        544            95/07/18                0 95/07/03        539            95/07/19                0 95/07/04        540            95/07/20                0 95/07/05        543            95/07/21                0 95/07/06        538            95/07/22                0 95/07/07        538            95/07/23                0 95/07/08        539            95/07/24                0 95/07/09        577            95/07/25                0 95/07/10        922            95/07/26               0 95/07/11        1002            95/07/27                0 95/07/12        1001            95/07/28                0 95/07/13        999            95/07/29                0 95/07/14        139            95/07/30                0 95/07/15          0            95/07/31              0 95/07/16          0
Se tember 23, 1995
: 26. Units in Test Status (Prior to Commercial Operation):
Forecast INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Achieved


~ ~
0
 
AVERAGE DAILY POWER LEVEL (MWe-Net)
DOCKET NO.
50-315 UNIT ONE DATE 02/Aug/95 COMPLETED BY DG Turner TELEPHONE 616-465-5901 DAY 95/07/01 95/07/02 95/07/03 95/07/04 95/07/05 95/07/06 95/07/07 95/07/08 95/07/09 95/07/10 95/07/11 95/07/12 95/07/13 95/07/14 95/07/15 95/07/16 July 1995 545 544 539 540 543 538 538 539 577 922 1002 1001 999 139 0
0 MONTH AVERAGE DAILY POWER LEVEL DAY 95/07/17 95/07/18 95/07/19 95/07/20 95/07/21 95/07/22 95/07/23 95/07/24 95/07/25 95/07/26 95/07/27 95/07/28 95/07/29 95/07/30 95/07/31 AVERAGE DAILY POWER LEVEL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
 
~
~
(s YI
(s YI


DOCKET NO:                   50-315 UNIT NAME:                    D.C. Cook Unit   1 COMPLETED BY:                G.F. Bussone 616-465-5901 TELEPHONE'ATE'AGE:
DOCKET NO:
August '8, 1995 Page 1 of 2 MONTHLY OPERATING   ACTIVITIES               JULY   1995 HIGHLIGHTS The unit entered this reporting period in Mode. 1 at 57% RTP                     with the West Main Feed Pump removed from service to perform planned maintenance activities.
UNIT NAME:
Reactor power was increased on July 9, 1995 at 1430 as the West Main Feed Pump was returned to service.         Reactor power reached 100% RTP on July 10, 1995 at 1126.
COMPLETED BY:
A low condenser vacuum turbine trip, and subsequent                     reactor trip, occurred on July 14, 1995 at 0426.
TELEPHONE'ATE'AGE:
Reactor power was increased to 88 RTP and Mode 1 was entered July 16, 1995 at 1010. Reactor power was subsequently reduced and the unit entered Mode 3 on July 16, 1995 at 2149 due to Main Transformer problems.
50-315 D.C.
The unit exited this reporting period in                 Mode 5 at 0% RTP.
Cook Unit 1
There were no challenges     to the pressurizer safety valves or power operated relief valv'es.
G.F.
Gross electrical generation for the       month           of June was 226520     MWH.
Bussone 616-465-5901 August '8, 1995 Page 1 of 2 MONTHLY OPERATING ACTIVITIES JULY 1995 HIGHLIGHTS The unit entered this reporting period in Mode.
DETAILS 07-09-95       1430       Commenced Reactor power increase.
1 at 57%
07-10-95      1126      Reactor power stabilized at                 100% RTP.
RTP with the West Main Feed Pump removed from service to perform planned maintenance activities.
07-14-95      0426      Reactor trip occurred, generated by low condenser vacuum turbine trip. Entered Reactor Mode 3.
Reactor power was increased on July 9, 1995 at 1430 as the West Main Feed Pump was returned to service.
07-15-95       2314     Reactor taken    critical.
Reactor power reached 100%
07-16-95       1010     Entered Reactor         Mode 1.
RTP on July 10, 1995 at 1126.
07-16-95      1233      Tripped Main Turbine.
A low condenser vacuum turbine trip, and subsequent reactor trip, occurred on July 14, 1995 at 0426.
Reactor power was increased to 88 RTP and Mode 1 was entered July 16, 1995 at 1010.
Reactor power was subsequently reduced and the unit entered Mode 3 on July 16, 1995 at 2149 due to Main Transformer problems.
The unit exited this reporting period in Mode 5 at 0% RTP.
There were no challenges to the pressurizer safety valves or power operated relief valv'es.
Gross electrical generation for the month of June was 226520 MWH.
DETAILS 07-09-95 1430 07-10-95 1126 07-14-95 0426 Commenced Reactor power increase.
Reactor power stabilized at 100% RTP.
Reactor trip occurred, generated by low condenser vacuum turbine trip.
Entered Reactor Mode 3.
07-15-95 2314 07-16-95 1010 07-16-95 1233 Reactor taken critical.
Entered Reactor Mode 1.
Tripped Main Turbine.


DOCKET NO:     50-315 UNIT NAME:      D.C. Cook Unit 1 COMPLETED BY:  G.F. Bussone TELEPHONE:      616-465-5901 DATE:          August 8, 1995 PAGE:          Page 2 of 2 MONTHLY OPERATING ACTIVITIES   JULY 1995 07-16-95 2149     Entered Reactor   Mode 3.
DOCKET NO:
07-29-95 0057    Commenced RCS cooldown.
UNIT NAME:
07-30-95 1117    Entered Reactor Mode 4.
COMPLETED BY:
07-31-95 0437    Entered Reactor   Mode 5.
TELEPHONE:
DATE:
PAGE:
50-315 D.C.
Cook Unit 1
G.F.
Bussone 616-465-5901 August 8, 1995 Page 2 of 2 MONTHLY OPERATING ACTIVITIES JULY 1995 07-16-95 07-29-95 07-30-95 07-31-95 2149 0057 1117 0437 Entered Reactor Mode 3.
Commenced RCS cooldown.
Entered Reactor Mode 4.
Entered Reactor Mode 5.


UNIT SHUTDOWNS AND POWER REDUCTIONS                                 UNIT NAME:       D.C. COOK UNIT 1 DATE:            August 8, 1995 REPORT MONTH: JULY 1995                                          COMPLETED BY:    G.F. Bussone .
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JULY 1995 UNIT NAME:
TELEPHONE:        616-465-5901   ~
DATE:
PAGE:            Page 1'of 1 METHOD OF SHUTTING   LICENSEE DURATION              DOWN       EVENT       SYSTEM   COMPONENT     CAUSE AND CORRECTIVE ACTION NO. DATE  TYPE      HOURS      REASON   REACTOR     REPORT NO. CODE     CODE           TO PREVENT RECURRENCE 317 950714   F       56. 1                             95-003     N/A     N/A           At 0426 Unit 1 received a reacto trip signal as a result of a turbine trip due to low condenser vacuum. The cause of the loss of condenser vacuum was a cracked socket weld connecting the drain trap to the condenser A steam dump control valve.
COMPLETED BY:
318 950716   F       371.5                             N/A         N/A     N/A           At 1153 while attempting to parallel the main generator to the grid excessive field voltage was applied. This resulted in damage   to the transformer core and the accumulation   of hydrogen in the transformer.
TELEPHONE:
1               2                                    3                    4                                5 F: Forced       Reason:                              Method:              Exhibit  G  Instructions      Exhibit  I:  Same S: Scheduled     A:   Equipment Failure (Explain)     1: Manual            for preparation of data                        Source B:   Maintenance or Test             2: Manual Scram      entry sheets for Licensee C:   Refueling                       3: Automatic Scram  Event Report (LER) File D:   Regulatory Restriction           4: Other (Explain)  (NUREG  0161)
PAGE:
E:  Operator Training and License Examination F:   Administrative G:   Operational Error (Explain)
D.C.
H:   Other (Explain)
COOK UNIT 1 August 8, 1995 G.F.
Bussone 616-465-5901
~
Page 1'of 1 DURATION NO.
DATE TYPE HOURS METHOD OF SHUTTING LICENSEE DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION REASON REACTOR REPORT NO.
CODE CODE TO PREVENT RECURRENCE 317 950714 F
: 56. 1 95-003 N/A N/A At 0426 Unit 1 received a reacto trip signal as a result of a turbine trip due to low condenser vacuum.
The cause of the loss of condenser vacuum was a cracked socket weld connecting the drain trap to the condenser A steam dump control valve.
318 950716 F
371.5 N/A N/A N/A At 1153 while attempting to parallel the main generator to the grid excessive field voltage was applied.
This resulted in damage to the transformer core and the accumulation of hydrogen in the transformer.
1 F:
Forced S:
Scheduled 2
Reason:
A:
Equipment Failure (Explain)
B:
Maintenance or Test C:
Refueling D:
Regulatory Restriction E:
Operator Training and License Examination F:
Administrative G:
Operational Error (Explain)
H:
Other (Explain) 3 Method:
1:
Manual 2:
Manual Scram 3:
Automatic Scram 4:
Other (Explain) 4Exhibit G Instructions for preparation of data entry sheets for Licensee Event Report (LER) File (NUREG 0161) 5Exhibit I:
Same Source


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e V
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'}}

Latest revision as of 14:07, 7 January 2025

Monthly Operating Rept for Jul 1995 for DC Cook Nuclear Plant Unit 1
ML17332A879
Person / Time
Site: Cook 
Issue date: 07/31/1995
From: Blind A, Doreen Turner
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9508150067
Download: ML17332A879 (11)


Text

PRIORITY (ACCELERATED RZDS PROCESSZNG)

REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)

ACCESSION NBR:9508150067 DOC.DATE: 95/07/31 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana M

05000315 p

AUTH.NAME AUTHOR AFFILIATION TURNER,D.G.

Indiana Michigan Power Co. (formerly Indiana S Michigan Ele BLIND,A.A.

Indiana Michigan Power Co.

(formerly Indiana

& Michigan, Ele R

RECIP.NAME RECIPIENT AFFILIATXON

SUBJECT:

Monthly operating rept for Jul 1995 for DC Cook Nuclear Plant Unit 1.W/950808 ltr.

DISTRIBUTION CODE:

IE24D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Monthly Operating Report (per Tech Specs NOTES RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/SPD/RRAB NRR/DISP/PIPB RGN3 EXTERNAL: LITCO BRYCE,J H

NRC PDR COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 RECXPIENT ID CODE/NAME HICKMAN,J NRR/DRPM/PECB NOAC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 D

N NOTE TO ALL "RZDS" RECZPZENTS:

PLEASE HELP US TO REDUCE WASTE!

CONTACT THE DOCUMENT CONTROL

DESK, ROOM OWFN 5D8 (415-2083)

TO ELZMZNATE YOUR NAME FROM DZSTRZBUTZON LZSTS FOR DOCUMENTS YOU DON'T NEED' TOTAL NUMBER OF COPIES REQUIRED:

LTTR 10 ENCL 10

indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 August 8,

1995 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

Pursuant to the requirements of Donald C.

Cook Nuclear Plant Unit 1 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of July 1995 is submitted.

Respectfully, A.A. Blind Plant Manager Attachment c:

NRC Region III D.R.

Hahn R.C. Callen S.

Hamming J.G.

Keppler INPO Records Center ANI Nuclear Engineering Department E.E. Fitzpatrick W.G. Smith, Jr.

S.J.

Brewer D.W. Paul S.H. Steinhart J.L. Leichner J.A.

Isom D.G. Turner E.A. Smarrella M.E. Russo 9508l50067 950731 PDR ADQCK 050003i5 R

PDR

~ /

N.R.CD OPERATING DATA REPORT DOCKET NO.

50-315 DATE 02/Aug/95 COMPLETED BY DG Turner TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D.

C.

Cook Unit 1

2. Reporting Period July 1995 notes
3. Licensed Thermal Power (MWt) 3250 4., Name Plate Rating (Gross MWe) 1152
5. Design Electrical Rating (Net MWe) 1020 6.

Maximum Dependable Capacity (GROSS MWe) 1056 7.

Maximum Dependable Capacity (Net MWe) 1000

8. If Changes Occur in Capacity Ratings (Items no.

3 through

7) Since Last Report Give Reasons 9.

Power Level To Which Restricted. If Any (Net MWe) 10'.

Reasons For Restrictions. If Any:

11. Hours in Reporting Period 12.

No. 'of Hrs. Reactor Was Critical

13. Reactor Reserve Shutdown Hours
14. Hours Generator on Line
15. Unit Reserve Shutdown Hours
16. Gross Therm.

Energy Gen.

(MWH) 17.

Gross Elect.

Energy Gen.

(MWH)

18. Net Elect.

Energy Gen.

(MWH)

19. Unit Service Factor
20. Unit Availability Factor
21. Unit Capacity Factor (MDC Net)
22. Unit Capacity Factor (DER Net) 23, Unit Forced Outage Rate 24 'hutdowns Scheduled over Next Six None This Mo.

Yr. to Date 744.0 5088.0 338.0 4682.0 0.0 0.0 315.4 4659.4 0.0 0.0 727724 14279008 226520 4645030 215173 4476987 42.4 91.6 42.4 91.6 28.9 88.0 28.4

'86.3 57.6 8.4 Months (Type, Date,and Cumm.

180408.0 136592.9 463.0 134483.0 321.0 396399585 128650470 123758302 75.4 75.4 68.4 66.6

5.9 Duration)

25. If Shut Down At End of Report Period, Estimated Date of Startup:

Se tember 23, 1995

26. Units in Test Status (Prior to Commercial Operation):

Forecast INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Achieved

0

AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

50-315 UNIT ONE DATE 02/Aug/95 COMPLETED BY DG Turner TELEPHONE 616-465-5901 DAY 95/07/01 95/07/02 95/07/03 95/07/04 95/07/05 95/07/06 95/07/07 95/07/08 95/07/09 95/07/10 95/07/11 95/07/12 95/07/13 95/07/14 95/07/15 95/07/16 July 1995 545 544 539 540 543 538 538 539 577 922 1002 1001 999 139 0

0 MONTH AVERAGE DAILY POWER LEVEL DAY 95/07/17 95/07/18 95/07/19 95/07/20 95/07/21 95/07/22 95/07/23 95/07/24 95/07/25 95/07/26 95/07/27 95/07/28 95/07/29 95/07/30 95/07/31 AVERAGE DAILY POWER LEVEL 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

~

~

(s YI

DOCKET NO:

UNIT NAME:

COMPLETED BY:

TELEPHONE'ATE'AGE:

50-315 D.C.

Cook Unit 1

G.F.

Bussone 616-465-5901 August '8, 1995 Page 1 of 2 MONTHLY OPERATING ACTIVITIES JULY 1995 HIGHLIGHTS The unit entered this reporting period in Mode.

1 at 57%

RTP with the West Main Feed Pump removed from service to perform planned maintenance activities.

Reactor power was increased on July 9, 1995 at 1430 as the West Main Feed Pump was returned to service.

Reactor power reached 100%

RTP on July 10, 1995 at 1126.

A low condenser vacuum turbine trip, and subsequent reactor trip, occurred on July 14, 1995 at 0426.

Reactor power was increased to 88 RTP and Mode 1 was entered July 16, 1995 at 1010.

Reactor power was subsequently reduced and the unit entered Mode 3 on July 16, 1995 at 2149 due to Main Transformer problems.

The unit exited this reporting period in Mode 5 at 0% RTP.

There were no challenges to the pressurizer safety valves or power operated relief valv'es.

Gross electrical generation for the month of June was 226520 MWH.

DETAILS 07-09-95 1430 07-10-95 1126 07-14-95 0426 Commenced Reactor power increase.

Reactor power stabilized at 100% RTP.

Reactor trip occurred, generated by low condenser vacuum turbine trip.

Entered Reactor Mode 3.

07-15-95 2314 07-16-95 1010 07-16-95 1233 Reactor taken critical.

Entered Reactor Mode 1.

Tripped Main Turbine.

DOCKET NO:

UNIT NAME:

COMPLETED BY:

TELEPHONE:

DATE:

PAGE:

50-315 D.C.

Cook Unit 1

G.F.

Bussone 616-465-5901 August 8, 1995 Page 2 of 2 MONTHLY OPERATING ACTIVITIES JULY 1995 07-16-95 07-29-95 07-30-95 07-31-95 2149 0057 1117 0437 Entered Reactor Mode 3.

Commenced RCS cooldown.

Entered Reactor Mode 4.

Entered Reactor Mode 5.

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JULY 1995 UNIT NAME:

DATE:

COMPLETED BY:

TELEPHONE:

PAGE:

D.C.

COOK UNIT 1 August 8, 1995 G.F.

Bussone 616-465-5901

~

Page 1'of 1 DURATION NO.

DATE TYPE HOURS METHOD OF SHUTTING LICENSEE DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION REASON REACTOR REPORT NO.

CODE CODE TO PREVENT RECURRENCE 317 950714 F

56. 1 95-003 N/A N/A At 0426 Unit 1 received a reacto trip signal as a result of a turbine trip due to low condenser vacuum.

The cause of the loss of condenser vacuum was a cracked socket weld connecting the drain trap to the condenser A steam dump control valve.

318 950716 F

371.5 N/A N/A N/A At 1153 while attempting to parallel the main generator to the grid excessive field voltage was applied.

This resulted in damage to the transformer core and the accumulation of hydrogen in the transformer.

1 F:

Forced S:

Scheduled 2

Reason:

A:

Equipment Failure (Explain)

B:

Maintenance or Test C:

Refueling D:

Regulatory Restriction E:

Operator Training and License Examination F:

Administrative G:

Operational Error (Explain)

H:

Other (Explain) 3 Method:

1:

Manual 2:

Manual Scram 3:

Automatic Scram 4:

Other (Explain) 4Exhibit G Instructions for preparation of data entry sheets for Licensee Event Report (LER) File (NUREG 0161) 5Exhibit I:

Same Source

e V

'