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=Text=
=Text=
{{#Wiki_filter:,           ._          . _    _ _ _ - _ _ _ _ _ _ . .          . . _
{{#Wiki_filter:,
TOLEDO
TOLEDO
  .  %ss       EDCON A Cocterior Energy Company Davis-Sesse Nuclear Power Statson                                                                                         1 6501 North State Route 2                                                                                                 l oak Harbor. OH 43449-9760 April 11,1997 KB-97-0068                                                                                                       l Documec Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Ladies and Gentlemen:
%ss EDCON A Cocterior Energy Company Davis-Sesse Nuclear Power Statson 1
Monthly Operating Report, March 1997 Davis-Besse Nuclear Power Station Unit I                                             ,
6501 North State Route 2 l
Enclosed is a copy of the Monthly Operating Report for Davis-Besse Nuclear Power                               i Station Unit I for the month of March 1997.
oak Harbor. OH 43449-9760 April 11,1997 KB-97-0068 Documec Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Ladies and Gentlemen:
Monthly Operating Report, March 1997 Davis-Besse Nuclear Power Station Unit I Enclosed is a copy of the Monthly Operating Report for Davis-Besse Nuclear Power i
Station Unit I for the month of March 1997.
If you have any questions, please contact E. C. Matranga at (419) 321-8369.
If you have any questions, please contact E. C. Matranga at (419) 321-8369.
Very truly yours, f                     '
Very truly yours, f
h I
h James H. Lash Plant Manager Davis-Besse Nuclear Power Station ECM/ljk Enclosure cc:
James H. Lash Plant Manager Davis-Besse Nuclear Power Station ECM/ljk                                                                                                       !
A. B. Beach NRC Region III Administrator l
Enclosure cc:       A. B. Beach NRC Region III Administrator l
A. G. Hansen g
A. G. Hansen                                                                                       g NRC Project Mtmager                                                                   Ib       '
NRC Project Mtmager Ib S. Stasek NRC Senior Resident Inspector 1
S. Stasek                                                                                           I NRC Senior Resident Inspector                                                                       i l
9704160114 970331
1 9704160114 970331 PDR         ADOCK 050003463 R                           PDR                                   %INhEhggggg$                ....-
%INhEhggggg$
PDR ADOCK 050003463 R
PDR


          ,                AVERAGE DAILY UNIT POWER LEVEL                       !
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-0346 UNIT Davis-Besse Unit 1 DATE April 1,1997 COMPLETED BY Eugene C. Matranga TELEPHONE 419/321-8369 MONTH March,1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)
DOCKET NO. 50-0346 UNIT Davis-Besse Unit 1 DATE April 1,1997 COMPLETED BY Eugene C. Matranga TELEPHONE 419/321-8369 MONTH March,1997 AVERAGE DAILY POWER LEVEL           AVERAGE DAILY POWER LEVEL   l DAY             (MWe-Net)             DAY             (MWe-Net) 1                   876             17                   881 2                   875             18                   883 1
DAY (MWe-Net) 1 876 17 881 2
3                  881             19                   883 4                   881             20                   881 5                   881             21                   877 6                   881             22                   883 1
875 18 883 3
7                    882             23                   882 I
881 19 883 4
8                    887             24                   883 9                   881             25                   878 10                   881             26                   881 11                   884             27                   877 12                   884             28                   874 13                   881             29                   890 14                   881             30                   878 15                   882             31                   882 16   ,
881 20 881 5
883
881 21 877 6
881 22 883 7
882 23 882 8
887 24 883 9
881 25 878 10 881 26 881 11 884 27 877 12 884 28 874 13 881 29 890 14 881 30 878 15 882 31 882 16 883


OPERATING DATA REPORT DOCKET NO     50-0346 DATE April 1,1997                 l COMPLETED BY       Euaene C. Matranaa         l TELEPHONE 419/321-8369 OPERATING STATUS
OPERATING DATA REPORT DOCKET NO 50-0346 DATE April 1,1997 COMPLETED BY Euaene C. Matranaa TELEPHONE 419/321-8369 OPERATING STATUS
: 1. Unit Name: Davis-Besse Unit 1                                                   Notes
: 1. Unit Name: Davis-Besse Unit 1 Notes
: 2. Reportina Period                                             March,1997
: 2. Reportina Period March,1997
: 3. Licensed Thermal Power (MWt)                                 2772
: 3. Licensed Thermal Power (MWt) 2772
: 4. Nameplate Ratina (Gross MWe)                                 925
: 4. Nameplate Ratina (Gross MWe) 925
: 5. Desian Electrical Ratina (Net MWe)                           906
: 5. Desian Electrical Ratina (Net MWe) 906
: 6. Maximum Dependable Capacity (Gross MWe)                       917
: 6. Maximum Dependable Capacity (Gross MWe) 917
: 7. Maximum Dependable Capacity (Net MWe)                         873
: 7. Maximum Dependable Capacity (Net MWe) 873
: 8. If Channes Occurin Capacity Ratinas (Items number 3 through 7) since last report, give reasons:
: 8. If Channes Occurin Capacity Ratinas (Items number 3 through 7) since last report, give reasons:
: 9. Power Level To Which Restricted, If Any (Net MWe):
: 9. Power Level To Which Restricted, If Any (Net MWe):
: 10. Reasons For Restrictions, If Any (Net MWe):
: 10. Reasons For Restrictions, If Any (Net MWe):
J This Month         Yr-to-Date     Cumulative
J This Month Yr-to-Date Cumulative
: 11. Hours in Reporting Perici                                           744.00           2,160.00     163,657.00           l
: 11. Hours in Reporting Perici 744.00 2,160.00 163,657.00
: 12. Number Of Hours Reactor Was Critical                                 744.00           2,160.00     108,355.97           j
: 12. Number Of Hours Reactor Was Critical 744.00 2,160.00 108,355.97 j
: 13. Reactor Reserve Shutdown Hours                                         0.00             0.00         5,532.00
: 13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00
: 14. Hours Generator On-Line                                             744.00           2,154.26     106,057.76
: 14. Hours Generator On-Line 744.00 2,154.26 106,057.76
: 15. Unit Reserve Shutdown Hours                                             0.00             0.00         1,732.50
: 15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50
: 16. Gross Thermal Energy Generated (MWH)                             2,059,707         5,938,043     276,516,888
: 16. Gross Thermal Energy Generated (MWH) 2,059,707 5,938,043 276,516,888
: 17. Gross Electrical Energy Generated (MWH)                             689,368         1,990,895     89,920.972           4
: 17. Gross Electrical Energy Generated (MWH) 689,368 1,990,895 89,920.972 4
: 18. Net Electrical Energy Generated (MWH)                               655,598         1,893,105     84,936,299
: 18. Net Electrical Energy Generated (MWH) 655,598 1,893,105 84,936,299
: 19. Unit Service Factor                                                 100.00             99.73                 64.80
: 19. Unit Service Factor 100.00 99.73 64.80
: 20. Unit Availability Factor                                             100.00             99.73                 65.86
: 20. Unit Availability Factor 100.00 99.73 65.86
: 21. Unit Capacity Factor (Using MDC Net)                                 100.94             100.39                 59.45
: 21. Unit Capacity Factor (Using MDC Net) 100.94 100.39 59.45
: 22. Unit Capacity Factor (Using DER Net)                                   97.26             96.74                 57.28
: 22. Unit Capacity Factor (Using DER Net) 97.26 96.74 57.28
: 23. Unit Forced Outage Rate                                                 0.00             0.26                 16.99
: 23. Unit Forced Outage Rate 0.00 0.26 16.99
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):                     Outaae considered for late April to replace RCP 2-2 motor has been canceled because temperatures have stabilized.
: 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Outaae considered for late April to replace RCP 2-2 motor has been canceled because temperatures have stabilized.
: 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):
: 26. Units in Test Status (Prior to Commercial Operation):
Forecast         Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION


l i
l i
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==SUMMARY==
==SUMMARY==
l March 1997 l
March 1997 Reactor power was maintained at approximately 100 percent full power until 0006 hours on March 2,1997, when a manual power reduction was initiated to perform turbine valve testing. Reactor power was reduced to i
Reactor power was maintained at approximately 100 percent full power until 0006 hours on March 2,1997, when a manual power reduction was initiated to perform turbine valve testing. Reactor power was reduced to i approximately 92 percent full power by 0039 hours, and control valve and ,
approximately 92 percent full power by 0039 hours, and control valve and stop valve testing were conducted. At the completion of testing at 0210 hours, power was gradually increased to approximately 100 percent full l
stop valve testing were conducted. At the completion of testing at 0210 !
power, which was achieved at 0304 hours.
hours, power was gradually increased to approximately 100 percent full l             power, which was achieved at 0304 hours.
1 Reactor power was maintained at approximately 100 percent full power until 0055 hours on March 30,1997, when a manual power reduction was initiated to perform turbine valve testing. Reactor power was reduced to approximately 92 percent full power by 0140 hours, and control valve and stop valve testing were conducted. At the completion of testing at 0218 hours, power was gradually increased to approximately 100 percent full power, which was achieved at 0308 hours.
1 Reactor power was maintained at approximately 100 percent full power until 0055 hours on March 30,1997, when a manual power reduction was initiated to perform turbine valve testing. Reactor power was reduced to approximately 92 percent full power by 0140 hours, and control valve and l
stop valve testing were conducted. At the completion of testing at 0218   l hours, power was gradually increased to approximately 100 percent full   I power, which was achieved at 0308 hours.
Reactor power was maintained at approximately 100 percent full power for the remainder of the month.
Reactor power was maintained at approximately 100 percent full power for the remainder of the month.
1 i
1 i
4
4


e     -
e UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT SHUTDOWNS AND POWER REDUCTIONS                                                     DOCKET NO.                         50-34P>
50-34P>
UNIT NAME Davis-Besse #1 .                                                    .
UNIT NAME Davis-Besse #1.
DATE April 1,1997,
DATE April 1,1997, Report Month March,1997 COMPLETED BY E. C. Matranga TELEPHONE (419) 321-8369 n
* Report Month March,1997                                                 COMPLETED BY E. C. Matranga TELEPHONE (419) 321-8369 n
E * $'
                                                                                      ~
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                        .        8g        "c    E * $'                     E-        E=                             Cause & Corrective
Cause & Corrective
                                                  )
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No.         Date F
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                                                                            $0           0 Action to Prevent Recurrence O
)
No Significant Shutdowns Or Power Reductions 1                   2                                                   3                                       4 F: Forced             Reason:                                           Method:                                 Exhibit G-Instructions S: Scheduled         A-Equipment Failure (Explain)                       1-Manual                               for Preparation of Data B-Maintenance or Test                             2-Manual Scram                         Entry Sheets for Licensee C-Refueling                                       3-Automatic Scram                       Event Report (LER) File (NUREG-D-Regulatory Restriction                           4-Continuation from                     0161)
E-Action to No.
E-Operator Training & License Examination             Previous Month F-Administrative                                   5-Load Reduction                     5 G-Operational Error (Explain)                     9-Other (Explain)                       Exhibit I - Same Source H-Other (Explain)
Date Re F
$5 y
j5c
$0 0
Prevent Recurrence O
No Significant Shutdowns Or Power Reductions 1
2 3
4 F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation from 0161)
E-Operator Training & License Examination Previous Month F-Administrative 5-Load Reduction 5
G-Operational Error (Explain) 9-Other (Explain)
Exhibit I - Same Source H-Other (Explain)
* Report challanges to Power Operated Relief Valves (PORVs) and Pressurizer Code Safety Valves (PCSVs)
* Report challanges to Power Operated Relief Valves (PORVs) and Pressurizer Code Safety Valves (PCSVs)
_ . - _ _ _ _ _ _          _ _ _ _ _          . _ _ _ _ _ _ _ _ _ _ _ _ _ .      _ _ _ - _ _ _ _ - _ _ _ _ _ _ _}}
-}}

Latest revision as of 21:15, 11 December 2024

Monthly Operating Rept for Mar 1997 for Davis-Besse Nuclear Power Station,Unit 1
ML20137T527
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/31/1997
From: Lash J, Matranga E
TOLEDO EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB-97-0068, KB-97-68, NUDOCS 9704160114
Download: ML20137T527 (5)
v • d • e


Text

,

TOLEDO

%ss EDCON A Cocterior Energy Company Davis-Sesse Nuclear Power Statson 1

6501 North State Route 2 l

oak Harbor. OH 43449-9760 April 11,1997 KB-97-0068 Documec Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Ladies and Gentlemen:

Monthly Operating Report, March 1997 Davis-Besse Nuclear Power Station Unit I Enclosed is a copy of the Monthly Operating Report for Davis-Besse Nuclear Power i

Station Unit I for the month of March 1997.

If you have any questions, please contact E. C. Matranga at (419) 321-8369.

Very truly yours, f

h James H. Lash Plant Manager Davis-Besse Nuclear Power Station ECM/ljk Enclosure cc:

A. B. Beach NRC Region III Administrator l

A. G. Hansen g

NRC Project Mtmager Ib S. Stasek NRC Senior Resident Inspector 1

9704160114 970331

%INhEhggggg$

PDR ADOCK 050003463 R

PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-0346 UNIT Davis-Besse Unit 1 DATE April 1,1997 COMPLETED BY Eugene C. Matranga TELEPHONE 419/321-8369 MONTH March,1997 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)

DAY (MWe-Net) 1 876 17 881 2

875 18 883 3

881 19 883 4

881 20 881 5

881 21 877 6

881 22 883 7

882 23 882 8

887 24 883 9

881 25 878 10 881 26 881 11 884 27 877 12 884 28 874 13 881 29 890 14 881 30 878 15 882 31 882 16 883

OPERATING DATA REPORT DOCKET NO 50-0346 DATE April 1,1997 COMPLETED BY Euaene C. Matranaa TELEPHONE 419/321-8369 OPERATING STATUS

1. Unit Name: Davis-Besse Unit 1 Notes
2. Reportina Period March,1997
3. Licensed Thermal Power (MWt) 2772
4. Nameplate Ratina (Gross MWe) 925
5. Desian Electrical Ratina (Net MWe) 906
6. Maximum Dependable Capacity (Gross MWe) 917
7. Maximum Dependable Capacity (Net MWe) 873
8. If Channes Occurin Capacity Ratinas (Items number 3 through 7) since last report, give reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any (Net MWe):

J This Month Yr-to-Date Cumulative

11. Hours in Reporting Perici 744.00 2,160.00 163,657.00
12. Number Of Hours Reactor Was Critical 744.00 2,160.00 108,355.97 j
13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00
14. Hours Generator On-Line 744.00 2,154.26 106,057.76
15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50
16. Gross Thermal Energy Generated (MWH) 2,059,707 5,938,043 276,516,888
17. Gross Electrical Energy Generated (MWH) 689,368 1,990,895 89,920.972 4
18. Net Electrical Energy Generated (MWH) 655,598 1,893,105 84,936,299
19. Unit Service Factor 100.00 99.73 64.80
20. Unit Availability Factor 100.00 99.73 65.86
21. Unit Capacity Factor (Using MDC Net) 100.94 100.39 59.45
22. Unit Capacity Factor (Using DER Net) 97.26 96.74 57.28
23. Unit Forced Outage Rate 0.00 0.26 16.99
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Outaae considered for late April to replace RCP 2-2 motor has been canceled because temperatures have stabilized.

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

l i

OPERATIONAL

SUMMARY

March 1997 Reactor power was maintained at approximately 100 percent full power until 0006 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> on March 2,1997, when a manual power reduction was initiated to perform turbine valve testing. Reactor power was reduced to i

approximately 92 percent full power by 0039 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br />, and control valve and stop valve testing were conducted. At the completion of testing at 0210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />, power was gradually increased to approximately 100 percent full l

power, which was achieved at 0304 hours0.00352 days <br />0.0844 hours <br />5.026455e-4 weeks <br />1.15672e-4 months <br />.

1 Reactor power was maintained at approximately 100 percent full power until 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> on March 30,1997, when a manual power reduction was initiated to perform turbine valve testing. Reactor power was reduced to approximately 92 percent full power by 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />, and control valve and stop valve testing were conducted. At the completion of testing at 0218 hours0.00252 days <br />0.0606 hours <br />3.604497e-4 weeks <br />8.2949e-5 months <br />, power was gradually increased to approximately 100 percent full power, which was achieved at 0308 hours0.00356 days <br />0.0856 hours <br />5.092593e-4 weeks <br />1.17194e-4 months <br />.

Reactor power was maintained at approximately 100 percent full power for the remainder of the month.

1 i

4

e UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-34P>

UNIT NAME Davis-Besse #1.

DATE April 1,1997, Report Month March,1997 COMPLETED BY E. C. Matranga TELEPHONE (419) 321-8369 n

E * $'

E=

Cause & Corrective

~

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E-Action to No.

Date Re F

$5 y

j5c

$0 0

Prevent Recurrence O

No Significant Shutdowns Or Power Reductions 1

2 3

4 F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation from 0161)

E-Operator Training & License Examination Previous Month F-Administrative 5-Load Reduction 5

G-Operational Error (Explain) 9-Other (Explain)

Exhibit I - Same Source H-Other (Explain)

  • Report challanges to Power Operated Relief Valves (PORVs) and Pressurizer Code Safety Valves (PCSVs)

-

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