ML20104B169: Difference between revisions

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TOLEDO
TOLEDO
                                                                                                                        %m EDISON A Cemenor Ecergy Cmnrany i OlSON M A7A i                                                                                                                           300 MADISON AVLNUE 101 E 00. OHIO 4305N1001 September 8, 1992 KB92-1886 Docket No. 50-346 License No. NPF-3 l                                       U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen Monthly Operating Report August 1992 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Desse
%m EDISON A Cemenor Ecergy Cmnrany i OlSON M A7A i
                                      -Nuclear Pover Station Unit No. 1 for the month of August 1992.
300 MADISON AVLNUE 101 E 00. OHIO 4305N1001 September 8, 1992 KB92-1886 Docket No. 50-346 License No. NPF-3 l
U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Gentlemen Monthly Operating Report August 1992 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Desse
-Nuclear Pover Station Unit No. 1 for the month of August 1992.
If you have any questions, please contact Bilal Sarsour at (419) 321-7384.
If you have any questions, please contact Bilal Sarsour at (419) 321-7384.
Very-truly yours, w
Very-truly yours, w
                                        !')(C(49
!')(C(49
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' (.-
                                        ' Louis F. Storz       GC Plant Manager Davis-Besse Nuclear Power Station                                                                               -
f/
BMS/ tid Enclosures cci   Mr. A. Bert Davis Regional Administrator, Region III Mr. J. B. Hopkins NRC Senior Project Manager
' Louis F. Storz GC Plant Manager Davis-Besse Nuclear Power Station BMS/ tid Enclosures cci Mr. A. Bert Davis Regional Administrator, Region III Mr. J. B. Hopkins NRC Senior Project Manager
                                                -Mr. Villiam Levis NRC Senior Resident Inspector h,   I mnn n                                                                                             M
-Mr. Villiam Levis NRC Senior Resident Inspector h,
                                                                                                                                              ~
I mnn n
I 9209150028 920s32 PDR R
~
                                          -ADOCK O$000346 PDR
9209150028 920s32 M
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PDR


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AVERAGE D AILY UNIT POWER LEVEL DOCKET NO. 50-346 INIT Davis-Besse D ATE September 8. 1992 COMPLETED BY Bilal Sarsour TELEPilONE (419)321-7384 MONUl             August 1992 DAY           AVERAGE D AILY POWER LEVEL                                                                       DAY                 AVER AGE DAILY POWER LEVEL (M We-Net I                                                                                                                 (MWe Net) 877                                                                           ,,
AVERAGE D AILY UNIT POWER LEVEL DOCKET NO.
878 3
50-346 Davis-Besse INIT D ATE September 8. 1992 COMPLETED BY Bilal Sarsour TELEPilONE (419)321-7384 MONUl August 1992 DAY AVERAGE D AILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (M We-Net I (MWe Net) 877 878 3
874                                                                                                                     875 2                                                                                                               IS 3                                 874                                                                         19                                       877
874 875 2
                                                .:                                875                                                                          20                                       877 5
IS 3
077                                                                                                                    879 21 6
874 877 19 875 877 20 077 879 5
876                                                                         ,,                                        875 7
21 876 875 6
873                                                                                                                     809 23 g                                  866                                                                                                                   871 3
873 809 7
9                                  871                                                                                                                   866 25 10 864                                                                                                                   866 26
23 866 871 g
                                                                                                                                                                                                                                          ~
3 871 866 9
jg                                   874                                                                        ,,                                        870 g                                     875                                                                                                                  870
25 864 866 10 26 874 870
                                                                                                                                                                ,g
~
                                              ,3 877                                                                        ,9 870 y                                     877                                                                        30 800 874                                                                                                                   855 15                                                                                                               31 16                                   822 INSTRUCTIONS On this format,hst the average daily unit power lesel in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
jg 875 870 g
,g 877 870
,3
,9 877 800 y
30 874 855 15 31 16 822 INSTRUCTIONS On this format,hst the average daily unit power lesel in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
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4 OPERATING D ATA REPORT DOCKET NO        50-346 DATE September 8, 1992 COMPLETED BY IIPhl Sarsour TELEPHONE U.TO 321-/384 OPERATING STATUS Davis-Besse Unit #1                         Notes
4 OPERATING D ATA REPORT 50-346 DOCKET NO DATE September 8, 1992 COMPLETED BY IIPhl Sarsour TELEPHONE U.TO 321-/384 OPERATING STATUS Davis-Besse Unit #1 Notes
: 1. Unit Name:
: 1. Unit Name:
: 2. Repordig Period:                                                                                 August 1992 2772
: 2. Repordig Period:
August 1992 2772
: 3. Licensed Thermal Power (MWt):
: 3. Licensed Thermal Power (MWt):
925
925
: 4. Nameplate Rating (Gross hlwe,.
: 4. Nameplate Rating (Gross hlwe,.
: 5. Design Electrical Rating (Net MWe):                                                                       906
906
: 5. Design Electrical Rating (Net MWe):
921
: 6. Maximum Dependable Capacity (Gross MWe):
: 6. Maximum Dependable Capacity (Gross MWe):
921
877
: 7. Maximurt Dependable Capacity (Net MWe):                                                                                 877
: 7. Maximurt Dependable Capacity (Net MWe):
: 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.lf Any (Net MWe):
: 9. Power Level To Which Restricted.lf Any (Net MWe):
: 10. Reasons For Restrictions,if Any; This Month         Yr..to-Date       Cumulative 11, Hours in Reporting Period 744.0             5,855.0                   123,504
: 10. Reasons For Restrictions,if Any; This Month Yr..to-Date Cumulative 744.0 5,855.0 123,504 11, Hours in Reporting Period
: 12. Number Of Hours Reactor Was Critical                                                                                       744.0             5,830.2                   72,006
: 12. Number Of Hours Reactor Was Critical 744.0 5,830.2 72,006 0.0 24.8 5,532.0
: 13. Reactor Reserse Shutdown Hours 0.0                 24.8               5,532.0
: 13. Reactor Reserse Shutdown Hours
: 14. Hours Generator on-Line                                                                                                   744.0             5,813.3                 69,846.4 0.0                   0.0               1,732.5
: 14. Hours Generator on-Line 744.0 5,813.3 69,846.4 0.0 0.0 1,732.5
: 15. Unit Re:erve Shutdown Hours
: 15. Unit Re:erve Shutdown Hours
: 16. Gross Therrr al Energy Generated (MbH)                                                                               2,046,461         15,984,682         172,593,975 678,321           5,339,402         57,232,779 17 Gross Electrical Energy Generated (MWH) 645,416           5,079,970         53,872,458 18.- Net Electrical Energy Generated (MWH)
: 16. Gross Therrr al Energy Generated (MbH) 2,046,461 15,984,682 172,593,975 678,321 5,339,402 57,232,779 17 Gross Electrical Energy Generated (MWH) 645,416 5,079,970 53,872,458 18.- Net Electrical Energy Generated (MWH) 100.0 99.3 56.6
: 19. Unit Service Factor                                                                                                        100.0                 99.3                   56.6
: 19. Unit Service Factor 100.0 99.3 58.0
: 20. Unit Availability Factor                                                                                                   100.0                   99.3                   58.0
: 20. Unit Availability Factor
: 21. Unit Capacity Factor (Using MDC Net)                                                                         _ _ _ _
: 21. Unit Capacity Factor (Using MDC Net) 98.9 98.9 49.7 95.7-95.8 48.I
98.9                   98.9                   49.7
: 22. Unit Capacity Factor (Using DER Net) 0.0 0.71 23.7
: 22. Unit Capacity Factor (Using DER Net)                                                                                       95.7-                  95.8                  48.I
: 23. Unit Forced Outage Rate
: 23. Unit Forced Outage Rate                                                                                                       0.0                  0.71                  23.7
: 24. Shutdowns Scheduled Over Next 6 Months (1ype. Date,and Duration of Each):
: 24. Shutdowns Scheduled Over Next 6 Months (1ype. Date,and Duration of Each):
: 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 ta Commercial Operation):                                                                                     Forecast         Achiesed INITIA L CRITICALITY INITI AL ELECTRICITY COMMERCIAL OPER ATION I
: 26. Units in Test Status (Prior ta Commercial Operation):
(o!77     I
Forecast Achiesed INITIA L CRITICALITY INITI AL ELECTRICITY COMMERCIAL OPER ATION I
(o!77 I


UNIT SIETDoWNS M7D FDWER FIDtKTIorG oemr re.       50-346 UNIT NAME Davis-Besse 91 oATz September 8, 1992
UNIT SIETDoWNS M7D FDWER FIDtKTIorG 50-346 oemr re.
* CQ 91ETED BY Silal Sarsour REroRT Mcenn August 1992                                         retz - gl,, 321-73s4
UNIT NAME Davis-Besse 91 oATz September 8, 1992 CQ 91ETED BY Silal Sarsour REroRT Mcenn August 1992 retz - gl,, 321-73s4 g.
: g.                                               @
c gg Licensee t4 Cause s Corr.cet,.
W    o                                                                  Cause s Corr.cet,.
W o
c          ,.,    o gg              Licensee                        t4 EO                       ^*ti'" t' no.        Dat. f         h         ,f: 3$$.               E"*"t
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                                                                  ...rt ,              h,.        !                    Pro.ent     r,   .
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3s               3;J                                   =         v No significant shptdowns           or power reductions.                                                                                 ,i l
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,i or power reductions.
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Method:                     Exhibit G - Instructions for Preparation of Data F; Forced      Reason:
1 l
5: Scheduled   A-Equipment Failure (Explain)                     1--Manual                   Entry Sheets for Licensee Event Report (LER)
l F; Forced Reason:
B-Nintentence or Test                             2-Manual Scram             File (NUPEG-0161)
Method:
C-Refueling                                       3-Automatic Scram D-Regulatory Restriction                         4-Continuation from E-Operator Training s License Examination               Previous Nnth         Exhibit I - Same source T-Administrative                                 5-Ioad Reduction
Exhibit G - Instructions for Preparation of Data 5: Scheduled A-Equipment Failure (Explain) 1--Manual Entry Sheets for Licensee Event Report (LER)
* Report challenges to Power Operated Relief Valves G-operational Error (Explain)                     9-Other (Explain)           (PORVs) and Pressurizer Code Safety valves (PCSVs)
B-Nintentence or Test 2-Manual Scram File (NUPEG-0161)
C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E-Operator Training s License Examination Previous Nnth Exhibit I - Same source T-Administrative 5-Ioad Reduction
* Report challenges to Power Operated Relief Valves G-operational Error (Explain) 9-Other (Explain)
(PORVs) and Pressurizer Code Safety valves (PCSVs)
H-Other (Explain)
H-Other (Explain)
{                                                             i
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Operational Summary August 1992 Reactor power was maintained at approximately 100 percent full power until 2400 hours on August 15, 1992, when a manual power reduction to approximately 83 percent was initiated to perform turbine valve testing and control rod drive (CRD) exercise testing.
Operational Summary August 1992 Reactor power was maintained at approximately 100 percent full power until 2400 hours on August 15, 1992, when a manual power reduction to approximately 83 percent was initiated to perform turbine valve testing and control rod drive (CRD) exercise testing.
After completion of turbine valve testing and CRD exercise testing, reactor power was maintained at 83 percent of full power due to lov system demand as requested by the Systems Operation Center.
After completion of turbine valve testing and CRD exercise testing, reactor power was maintained at 83 percent of full power due to lov system demand as requested by the Systems Operation Center.
Line 104: Line 129:
At 0015 hours on August 29, 1992, reactor power was slowly increased to approximately 100 petcent full power, which was achieved at 0305 hours on August 29, 1992.
At 0015 hours on August 29, 1992, reactor power was slowly increased to approximately 100 petcent full power, which was achieved at 0305 hours on August 29, 1992.
Reactor power was-maintained at approximately 100 percent until 2200 hours on August' 29, 1992, when a manual pover reduction to approximately 91 percent was initiated due to lov system demand as requested by the Systems Operation Center.
Reactor power was-maintained at approximately 100 percent until 2200 hours on August' 29, 1992, when a manual pover reduction to approximately 91 percent was initiated due to lov system demand as requested by the Systems Operation Center.
At 0530 hours on August 31, 1992, reactor power was slowly increased to approximately 100 percent full power, which was achieved at 0610 honrs on j
At 0530 hours on August 31, 1992, reactor power was slowly increased to approximately 100 percent full power, which was achieved at 0610 honrs on August 31, 1992, and maintained at this power level for the rest of the month.
August 31, 1992, and maintained at this power level for the rest of the month.
j I
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_ - __}}
___ _ - __}}

Latest revision as of 03:33, 13 December 2024

Monthly Operating Rept for Aug 1992 for DBNPS Unit 1.W/
ML20104B169
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 08/31/1992
From: Sarsour B, Storz L
TOLEDO EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB92-1886, NUDOCS 9209150028
Download: ML20104B169 (5)


Text

,

TOLEDO

%m EDISON A Cemenor Ecergy Cmnrany i OlSON M A7A i

300 MADISON AVLNUE 101 E 00. OHIO 4305N1001 September 8, 1992 KB92-1886 Docket No. 50-346 License No. NPF-3 l

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555 Gentlemen Monthly Operating Report August 1992 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Desse

-Nuclear Pover Station Unit No. 1 for the month of August 1992.

If you have any questions, please contact Bilal Sarsour at (419) 321-7384.

Very-truly yours, w

!')(C(49

' (.-

f/

' Louis F. Storz GC Plant Manager Davis-Besse Nuclear Power Station BMS/ tid Enclosures cci Mr. A. Bert Davis Regional Administrator, Region III Mr. J. B. Hopkins NRC Senior Project Manager

-Mr. Villiam Levis NRC Senior Resident Inspector h,

I mnn n

~

9209150028 920s32 M

I PDR -ADOCK O$000346 R

PDR

l I'

AVERAGE D AILY UNIT POWER LEVEL DOCKET NO.

50-346 Davis-Besse INIT D ATE September 8. 1992 COMPLETED BY Bilal Sarsour TELEPilONE (419)321-7384 MONUl August 1992 DAY AVERAGE D AILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (M We-Net I (MWe Net) 877 878 3

874 875 2

IS 3

874 877 19 875 877 20 077 879 5

21 876 875 6

873 809 7

23 866 871 g

3 871 866 9

25 864 866 10 26 874 870

~

jg 875 870 g

,g 877 870

,3

,9 877 800 y

30 874 855 15 31 16 822 INSTRUCTIONS On this format,hst the average daily unit power lesel in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

pa n ? )

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4 OPERATING D ATA REPORT 50-346 DOCKET NO DATE September 8, 1992 COMPLETED BY IIPhl Sarsour TELEPHONE U.TO 321-/384 OPERATING STATUS Davis-Besse Unit #1 Notes

1. Unit Name:
2. Repordig Period:

August 1992 2772

3. Licensed Thermal Power (MWt):

925

4. Nameplate Rating (Gross hlwe,.

906

5. Design Electrical Rating (Net MWe):

921

6. Maximum Dependable Capacity (Gross MWe):

877

7. Maximurt Dependable Capacity (Net MWe):
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted.lf Any (Net MWe):
10. Reasons For Restrictions,if Any; This Month Yr..to-Date Cumulative 744.0 5,855.0 123,504 11, Hours in Reporting Period
12. Number Of Hours Reactor Was Critical 744.0 5,830.2 72,006 0.0 24.8 5,532.0
13. Reactor Reserse Shutdown Hours
14. Hours Generator on-Line 744.0 5,813.3 69,846.4 0.0 0.0 1,732.5
15. Unit Re:erve Shutdown Hours
16. Gross Therrr al Energy Generated (MbH) 2,046,461 15,984,682 172,593,975 678,321 5,339,402 57,232,779 17 Gross Electrical Energy Generated (MWH) 645,416 5,079,970 53,872,458 18.- Net Electrical Energy Generated (MWH) 100.0 99.3 56.6
19. Unit Service Factor 100.0 99.3 58.0
20. Unit Availability Factor
21. Unit Capacity Factor (Using MDC Net) 98.9 98.9 49.7 95.7-95.8 48.I
22. Unit Capacity Factor (Using DER Net) 0.0 0.71 23.7
23. Unit Forced Outage Rate
24. Shutdowns Scheduled Over Next 6 Months (1ype. Date,and Duration of Each):
25. If Shut Down At End Of Report Period, Estimated Date of Startup:
26. Units in Test Status (Prior ta Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITI AL ELECTRICITY COMMERCIAL OPER ATION I

(o!77 I

UNIT SIETDoWNS M7D FDWER FIDtKTIorG 50-346 oemr re.

UNIT NAME Davis-Besse 91 oATz September 8, 1992 CQ 91ETED BY Silal Sarsour REroRT Mcenn August 1992 retz - gl,, 321-73s4 g.

c gg Licensee t4 Cause s Corr.cet,.

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v No significant shptdowns

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l F; Forced Reason:

Method:

Exhibit G - Instructions for Preparation of Data 5: Scheduled A-Equipment Failure (Explain) 1--Manual Entry Sheets for Licensee Event Report (LER)

B-Nintentence or Test 2-Manual Scram File (NUPEG-0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E-Operator Training s License Examination Previous Nnth Exhibit I - Same source T-Administrative 5-Ioad Reduction

  • Report challenges to Power Operated Relief Valves G-operational Error (Explain) 9-Other (Explain)

(PORVs) and Pressurizer Code Safety valves (PCSVs)

H-Other (Explain)

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Operational Summary August 1992 Reactor power was maintained at approximately 100 percent full power until 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> on August 15, 1992, when a manual power reduction to approximately 83 percent was initiated to perform turbine valve testing and control rod drive (CRD) exercise testing.

After completion of turbine valve testing and CRD exercise testing, reactor power was maintained at 83 percent of full power due to lov system demand as requested by the Systems Operation Center.

At 0817 hours0.00946 days <br />0.227 hours <br />0.00135 weeks <br />3.108685e-4 months <br /> on August 16, 1992, reactor power was slowly increased to approximately 100 percent, which was achieved at 0941 hours0.0109 days <br />0.261 hours <br />0.00156 weeks <br />3.580505e-4 months <br /> on August 16, 1992.

Reactor power was maintained at approximately 100 percent full power until 0122 hours0.00141 days <br />0.0339 hours <br />2.017196e-4 weeks <br />4.6421e-5 months <br /> on August 23, 1992, when a manual power reduction ta approximately 92 percent was initiated due to lov system demand as requested by the Systems Operation Center.

At 0835 hours0.00966 days <br />0.232 hours <br />0.00138 weeks <br />3.177175e-4 months <br /> on August 23, 1992, reactor power was slowly increased to approximately 100 percent full power, which was achieved at 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br /> on August 23, 1992.

Reactor power was maintained at approximately 100 percent until 2325 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.846625e-4 months <br /> on August 28, 1992, when a manual power reduction to approximately 94 percent was initiated due to High Pres.'ure Feedvater Heater 2-6 level controller LC361B problems.

At 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> on August 29, 1992, reactor power was slowly increased to approximately 100 petcent full power, which was achieved at 0305 hours0.00353 days <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br /> on August 29, 1992.

Reactor power was-maintained at approximately 100 percent until 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on August' 29, 1992, when a manual pover reduction to approximately 91 percent was initiated due to lov system demand as requested by the Systems Operation Center.

At 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> on August 31, 1992, reactor power was slowly increased to approximately 100 percent full power, which was achieved at 0610 honrs on August 31, 1992, and maintained at this power level for the rest of the month.

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