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  .o AVERAGE DAILY UNIT POWER LEVEL DOC K ET .s'O.
.o AVERAGE DAILY UNIT POWER LEVEL 50-346 DOC K ET.s'O.
50-346
3gy Davis-Besse Unit 1 DATE COMPLETED BY Bilal Sarsour TELEPilONE (419) 259-5000, Ext. 384 MONT11 November, 1981 DAY AVERAGE DAILY F0WER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
                                                                                      ,                3gy     Davis-Besse Unit 1 DATE                 _
(MWe Net) 1 772
COMPLETED BY       Bilal Sarsour
=
              '                                                                                  TELEPilONE     (419) 259-5000, Ext. 384 MONT11 November, 1981 DAY       AVERAGE DAILY F0WER LEVEL                               DAY     AVERAGE DAILY POWER LEVEL (MWe Net)                                                   (MWe Net) 1                     772                                                             0
17 0
                                                        =                     17 2                     772                                       18                   0 3                     771                                       39                   0 4     .                772                                       20                   0 5                     631                                 .
2 772 18 0
21                   0 6                     657                                       22                   0 7                     519                                       23                   0 8                     512                                       2.g                 0 1
3 771 39 0
9                    515                                         25                   0 10                   511                                         26                   0 II.                   511                                         27                   0 12                     510                                                             0 28 13                     460                                       29                   0 34                         2                                                           0 30 15                       0                                       3; 16                       0 INSTRUCTIONS On this formai. list the a>cra;.c daily unit power levelin MWe Net for each day in the reportmg month. Compute to the nearest whole megawait.
4 772 20 0
5 631 21 0
6 657 22 0
7 519 23 0
8 512 2.g 0
1 9
515 25 0
10 511 26 0
II.
511 27 0
12 510 28 0
13 460 0
29 34 2
30 0
15 0
3; 16 0
INSTRUCTIONS On this formai. list the a>cra;.c daily unit power levelin MWe Net for each day in the reportmg month. Compute to the nearest whole megawait.
(9/77) 8211110387 811207 DR ADOCK 05000346 PDR
(9/77) 8211110387 811207 DR ADOCK 05000346 PDR


                                                                                                        =_     _
=_
            ~
L
L OPERATING DATA REPORT DOCKET NO.       50-346 DATE CO51PLETED BY       Rilal Sarsour TELEP110NE       (419) 259-5000, Ext. 384 OPERATING STATUS Davis-Besse Unit 1                              Notes
~
OPERATING DATA REPORT DOCKET NO.
50-346 DATE CO51PLETED BY Rilal Sarsour TELEP110NE (419) 259-5000, Ext. 384 OPERATING STATUS
: 1. Unit Name:
: 1. Unit Name:
: 2. Reporting Period:     November, 1981                                                                               .
Davis-Besse Unit 1 Notes
: 3. Licenwd Thermal Power (StWt):               2772
: 2. Reporting Period:
: 4. Nameplate Rating (Gross 5tWe):               925
November, 1981
: 5. Desiga Electrical Rating (Net 5tWe):         906
: 3. Licenwd Thermal Power (StWt):
: 6. 71aximum Dependable Capacity (Gross $1We):             934
2772
: 7. Afaximum Dependable Capacity (Net 31We):               890
: 4. Nameplate Rating (Gross 5tWe):
925 906
: 5. Desiga Electrical Rating (Net 5tWe):
: 6. 71aximum Dependable Capacity (Gross $1We):
934
: 7. Afaximum Dependable Capacity (Net 31We):
890
: 8. If Chan;;es Occur in Cipacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:
: 8. If Chan;;es Occur in Cipacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:
: 9. Power Lesel To Which Restricted,if Any (Net 5fWe):                       ,
: 9. Power Lesel To Which Restricted,if Any (Net 5fWe):
: 10. Reasons For Restrictions,if Any:
: 10. Reasons For Restrictions,if Any:
This 5fonth               Yr..to Date         Cumulative II. liours in Reporting Period                                   720                   8,016           37,325
This 5fonth Yr..to Date Cumulative II. liours in Reporting Period 720 8,016 37,325
: 12. Number OfIlours Reactor Was Critica]                         314.8                 5.426.1         19.810.3                 .
: 12. Number OfIlours Reactor Was Critica]
: 13. Reactor Reserve Shutdown llours                             405.2                   849.7           3.731.8
314.8 5.426.1 19.810.3
: 14. Ilours Generator On Line                                     313.1                 5.224.4         18.272.2
: 13. Reactor Reserve Shutdown llours 405.2 849.7 3.731.8
: 15. Unit Re>ene Shutdown flours                                   0                         0             1.731.4
: 14. Ilours Generator On Line 313.1 5.224.4 18.272.2
: 16. Gross Thermal Energy Generated (51Wil)                 667,941         12,366,497             39,271,303                 .
: 15. Unit Re>ene Shutdown flours 0
: 17. Gross Elect ical Energy Generated (51Wil)               202.905_,..         4.098.941           13.074.275
0 1.731.4
: 18. Net Electrical Energy Generated (51Wil)                 181.671             1.839.771           12.104.272
: 16. Gross Thermal Energy Generated (51Wil) 667,941 12,366,497 39,271,303
: 19. Unit Senice Factor                                           43.5                     65.2               49.7
: 17. Gross Elect ical Energy Generated (51Wil) 202.905_,..
: 20. Unit Availability Factor                                       43.5                     65.2               54.6
4.098.941 13.074.275
: 21. Unit Capacity Factor (Using SIDC Net) -                       28.7                     53.8               38.2
: 18. Net Electrical Energy Generated (51Wil) 181.671 1.839.771 12.104.272
: 22. Unit Capacity Factor (U>ing DER Net)                           28.2                     52.9               37.5
: 19. Unit Senice Factor 43.5 65.2 49.7
: 23. Unit Forced Outage Rate                                         0                       26.9               25.3
: 20. Unit Availability Factor 43.5 65.2 54.6
: 21. Unit Capacity Factor (Using SIDC Net) -
28.7 53.8 38.2
: 22. Unit Capacity Factor (U>ing DER Net) 28.2 52.9 37.5
: 23. Unit Forced Outage Rate 0
26.9 25.3
: 24. Shutdowns Scheduled Oser Next 6 51onths (Type. Date,and Duration n. Each t:
: 24. Shutdowns Scheduled Oser Next 6 51onths (Type. Date,and Duration n. Each t:
Refueling Outage               From February 26, 1982 - Pay 21, 1982                                                       .
Refueling Outage From February 26, 1982 - Pay 21, 1982
: 25. If Shut Down At $nd 0,f Report Period. Estimated Date of Startup: . _ _       December 2. 1981
: 25. If Shut Down At $nd 0,f Report Period. Estimated Date of Startup:. _ _
: 26. Unit, In Test Statu> (Prior to Commercial Operation):                         Forecast             Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY CO\1NIERCIA L OPER AllON (9/771
December 2. 1981
: 26. Unit, In Test Statu> (Prior to Commercial Operation):
Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY CO\\1NIERCIA L OPER AllON (9/771


9 DOCKET NO.         50-346                   ,
9 DOCKET NO.
UNIT SHUTDOWNS AND POW' t REDUCTIONS                             UNIT NAME         Davis-Hosse Unit 1         ,
50-346 UNIT SHUTDOWNS AND POW' t REDUCTIONS UNIT NAME Davis-Hosse Unit 1 DATE COMPLETED ilY Bilal Sarsour REPORT MONTil November, 1981 TELEPIIONE (41H 259-5000. Ext.
DATE COMPLETED ilY         Bilal Sarsour REPORT MONTil November, 1981                               TELEPIIONE         (41H 259-5000. Ext.
384
384
    ~
~
e.
e.
_    E                                 E
E E
                              ;,        .! ?     3       $ .Y 5 jss Licensee     jg         {%                         Cause & Corrective Action to No.         Date     R         5g       i                     Event       g          e.1 H
.! ?
5        $      j,3 g       Report
3
* idu?        yV                        Prevent Recurrence-5 17 ,     18 11 7     F           0       A         5                                               Reactor power was reduced due to a leaking extraction steam line expan-sion bellows in No. 1 Low Pressure Turbine to No.1 De'a erator.
$.Y 5 Licensee jg
18       81 11 14   S         406.9       A         1                                               The unit was taken off line due to                               .
{%
        '                                                                                                    indications of further degradation of extraction line bellows.
Cause & Corrective g
''.                                                                                                          See Operational Summary for further details.
e.1 Action to No.
I                     2                                                       3                                     4 F: Forced           Reason:                                                 Method:                                 Exhibit G - Instructions S: Schedu!cd         A.Eituipment Failure (Explain)                           1 Manual                               for Preparation of Data D. Maintenance of Test                                 2 Manual Scrani.                       Entry Sheets for Licensee C-Refueling                                             3 Automatic Scram.          .
Date R
Event Report (LER) File (NllREG-D 'tei;ulstory Restriction                             4 Continuation from Previous Month     0161) l.Operato Ti ;ning& License ExPmination                 5-Load Reduction F Administrative                                       9-Other (Explain)                 S
5g i
* G Operational Etrur (Explain)                                                                   Exliibit 1 - Same Source C1/77)                   Il Other (Explain)
jss Event idu?
                                      .                                          i
yV Prevent Recurrence-H 5
j,3 g Report
* 5 17,
18 11 7 F
0 A
5 Reactor power was reduced due to a leaking extraction steam line expan-sion bellows in No. 1 Low Pressure Turbine to No.1 De' erator.
a 18 81 11 14 S
406.9 A
1 The unit was taken off line due to indications of further degradation of extraction line bellows.
See Operational Summary for further details.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G - Instructions S: Schedu!cd A.Eituipment Failure (Explain) 1 Manual for Preparation of Data D. Maintenance of Test 2 Manual Scrani.
Entry Sheets for Licensee Event Report (LER) File (NllREG-C-Refueling 3 Automatic Scram.
0161)
D 'tei;ulstory Restriction 4 Continuation from Previous Month l.Operato Ti ;ning& License ExPmination 5-Load Reduction F Administrative 9-Other (Explain)
S G Operational Etrur (Explain)
Exliibit 1 - Same Source C1/77)
Il Other (Explain) i


OPERATIONAL  
OPERATIONAL  


==SUMMARY==
==SUMMARY==
November, 1981
November, 1981
                                                                                      ~
~
I 11/1/81 - 11/12/81   Reactor power was maintained at 95% (power was reduced to 95% due to a leaking extraction steam bellows expansion joint     i in No. 1 Low Pressure Turbine to No. 1 Deserator) until 0925 hours on November 5, 1981, when reactor power was reduced to approximately 83%. This power level was maintained until November 7, 1981, when it was further reduced to 66%. These reductions of power were necessary due to indications of         (
11/1/81 - 11/12/81 Reactor power was maintained at 95% (power was reduced to 95% due to a leaking extraction steam bellows expansion joint in No. 1 Low Pressure Turbine to No. 1 Deserator) until 0925 hours on November 5, 1981, when reactor power was reduced to approximately 83%. This power level was maintained until November 7, 1981, when it was further reduced to 66%. These reductions of power were necessary due to indications of further degradation of the expansion joint.
further degradation of the expansion joint.                       l 11/13/81 - 11/30/81   A manual reduction of reactor power was initiated at 1900 hours on 11/13/81 for an expansion joint outage. The unit was manually taken off-line at 0103 hours on November 14, 1981, for the planned expansion joint outage. A total of five expansion joints were replaced during this outage.
11/13/81 - 11/30/81 A manual reduction of reactor power was initiated at 1900 hours on 11/13/81 for an expansion joint outage.
The unit was manually taken off-line at 0103 hours on November 14, 1981, for the planned expansion joint outage. A total of five expansion joints were replaced during this outage.
e e
e e
E e
E e
Line 90: Line 140:
4
4


c .
c.
November, 1981 DATE:
DATE:
REFUELING INFORMATION
November, 1981 REFUELING INFORMATION 1.
: 1. Name of facility:           Davis-Besse Unit 1 February 26, 1982
Name of facility:
: 2. S:heduled date for next refueling shutdown:
Davis-Besse Unit 1 February 26, 1982 2.
May 21, 1982 3.,   Scheduled date for restart following refueling:
S:heduled date for next refueling shutdown:
: 4. Will refueling or resumption of operation thereafter         require a technical If answer is yes, what, specification change or other license amendment?
May 21, 1982 3., Scheduled date for restart following refueling:
Will refueling or resumption of operation thereafter require a technical 4.
If answer is yes, what, specification change or other license amendment?
in generel, will these be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Ccamittee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)?
in generel, will these be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Ccamittee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)?
Reload analysis is scheduled for completion as of January, 1982. No technical specification changes or other license amendments identified to date.
Reload analysis is scheduled for completion as of January, 1982.
: 5. Scheduled date(s) for submitting proposed licensing action and supporting information.           February. 1982 e.g., new or
No technical specification changes or other license amendments identified to date.
: 6. Important licensing considerations associated with refueling, different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.                     -
Scheduled date(s) for submitting proposed licensing action and supporting 5.
information.
February. 1982 Important licensing considerations associated with refueling, e.g., new or 6.
different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
None identified to date J
None identified to date J
: 7. The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool.                                         ,44 - Spent Fuel Assemblies 177                       (b)         8 - New Fuel Assemblics (a)
The number of fuel assemblics (a) in the core and (b) in the spent fuel 7.
: 8. The present liaensed spent fuel pool storage capacity and the size of any incretse in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.                            .
storage pool.
735                 Increase size by             0 (zero)
,44 - Spent Fuel Assemblies (a) 177 (b) 8 - New Fuel Assemblics The present liaensed spent fuel pool storage capacity and the size of any 8.
Present
incretse in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
: 9. The projected date of the last refueling that can le' discharged to the spent          .
Present 735 Increase size by 0 (zero) can le' discharged to the spent 9.
fuel pool assuming the present licensed capacity.
The projected date of the last refueling that fuel pool assuming the present licensed capacity.
fuel Date 19BC - assuming ability to unload the entire oore into the spent pool is maintained                                             .
fuel 19BC - assuming ability to unload the entire oore into the spent Date pool is maintained
                                                                      -}}
-}}

Latest revision as of 18:33, 16 December 2024

Monthly Operating Rept for Nov 1981
ML20066D534
Person / Time
Site: Davis Besse 
Issue date: 12/07/1981
From: Sarsour B
TOLEDO EDISON CO.
To:
Shared Package
ML20066D533 List:
References
NUDOCS 8211110387
Download: ML20066D534 (5)


Text

.

.o AVERAGE DAILY UNIT POWER LEVEL 50-346 DOC K ET.s'O.

3gy Davis-Besse Unit 1 DATE COMPLETED BY Bilal Sarsour TELEPilONE (419) 259-5000, Ext. 384 MONT11 November, 1981 DAY AVERAGE DAILY F0WER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe Net) 1 772

=

17 0

2 772 18 0

3 771 39 0

4 772 20 0

5 631 21 0

6 657 22 0

7 519 23 0

8 512 2.g 0

1 9

515 25 0

10 511 26 0

II.

511 27 0

12 510 28 0

13 460 0

29 34 2

30 0

15 0

3; 16 0

INSTRUCTIONS On this formai. list the a>cra;.c daily unit power levelin MWe Net for each day in the reportmg month. Compute to the nearest whole megawait.

(9/77) 8211110387 811207 DR ADOCK 05000346 PDR

=_

L

~

OPERATING DATA REPORT DOCKET NO.

50-346 DATE CO51PLETED BY Rilal Sarsour TELEP110NE (419) 259-5000, Ext. 384 OPERATING STATUS

1. Unit Name:

Davis-Besse Unit 1 Notes

2. Reporting Period:

November, 1981

3. Licenwd Thermal Power (StWt):

2772

4. Nameplate Rating (Gross 5tWe):

925 906

5. Desiga Electrical Rating (Net 5tWe):
6. 71aximum Dependable Capacity (Gross $1We):

934

7. Afaximum Dependable Capacity (Net 31We):

890

8. If Chan;;es Occur in Cipacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:
9. Power Lesel To Which Restricted,if Any (Net 5fWe):
10. Reasons For Restrictions,if Any:

This 5fonth Yr..to Date Cumulative II. liours in Reporting Period 720 8,016 37,325

12. Number OfIlours Reactor Was Critica]

314.8 5.426.1 19.810.3

13. Reactor Reserve Shutdown llours 405.2 849.7 3.731.8
14. Ilours Generator On Line 313.1 5.224.4 18.272.2
15. Unit Re>ene Shutdown flours 0

0 1.731.4

16. Gross Thermal Energy Generated (51Wil) 667,941 12,366,497 39,271,303
17. Gross Elect ical Energy Generated (51Wil) 202.905_,..

4.098.941 13.074.275

18. Net Electrical Energy Generated (51Wil) 181.671 1.839.771 12.104.272
19. Unit Senice Factor 43.5 65.2 49.7
20. Unit Availability Factor 43.5 65.2 54.6
21. Unit Capacity Factor (Using SIDC Net) -

28.7 53.8 38.2

22. Unit Capacity Factor (U>ing DER Net) 28.2 52.9 37.5
23. Unit Forced Outage Rate 0

26.9 25.3

24. Shutdowns Scheduled Oser Next 6 51onths (Type. Date,and Duration n. Each t:

Refueling Outage From February 26, 1982 - Pay 21, 1982

25. If Shut Down At $nd 0,f Report Period. Estimated Date of Startup:. _ _

December 2. 1981

26. Unit, In Test Statu> (Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY CO\\1NIERCIA L OPER AllON (9/771

9 DOCKET NO.

50-346 UNIT SHUTDOWNS AND POW' t REDUCTIONS UNIT NAME Davis-Hosse Unit 1 DATE COMPLETED ilY Bilal Sarsour REPORT MONTil November, 1981 TELEPIIONE (41H 259-5000. Ext.

384

~

e.

E E

.! ?

3

$.Y 5 Licensee jg

{%

Cause & Corrective g

e.1 Action to No.

Date R

5g i

jss Event idu?

yV Prevent Recurrence-H 5

j,3 g Report

  • 5 17,

18 11 7 F

0 A

5 Reactor power was reduced due to a leaking extraction steam line expan-sion bellows in No. 1 Low Pressure Turbine to No.1 De' erator.

a 18 81 11 14 S

406.9 A

1 The unit was taken off line due to indications of further degradation of extraction line bellows.

See Operational Summary for further details.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Schedu!cd A.Eituipment Failure (Explain) 1 Manual for Preparation of Data D. Maintenance of Test 2 Manual Scrani.

Entry Sheets for Licensee Event Report (LER) File (NllREG-C-Refueling 3 Automatic Scram.

0161)

D 'tei;ulstory Restriction 4 Continuation from Previous Month l.Operato Ti ;ning& License ExPmination 5-Load Reduction F Administrative 9-Other (Explain)

S G Operational Etrur (Explain)

Exliibit 1 - Same Source C1/77)

Il Other (Explain) i

OPERATIONAL

SUMMARY

November, 1981

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11/1/81 - 11/12/81 Reactor power was maintained at 95% (power was reduced to 95% due to a leaking extraction steam bellows expansion joint in No. 1 Low Pressure Turbine to No. 1 Deserator) until 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> on November 5, 1981, when reactor power was reduced to approximately 83%. This power level was maintained until November 7, 1981, when it was further reduced to 66%. These reductions of power were necessary due to indications of further degradation of the expansion joint.

11/13/81 - 11/30/81 A manual reduction of reactor power was initiated at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on 11/13/81 for an expansion joint outage.

The unit was manually taken off-line at 0103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br /> on November 14, 1981, for the planned expansion joint outage. A total of five expansion joints were replaced during this outage.

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DATE:

November, 1981 REFUELING INFORMATION 1.

Name of facility:

Davis-Besse Unit 1 February 26, 1982 2.

S:heduled date for next refueling shutdown:

May 21, 1982 3., Scheduled date for restart following refueling:

Will refueling or resumption of operation thereafter require a technical 4.

If answer is yes, what, specification change or other license amendment?

in generel, will these be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Ccamittee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)?

Reload analysis is scheduled for completion as of January, 1982.

No technical specification changes or other license amendments identified to date.

Scheduled date(s) for submitting proposed licensing action and supporting 5.

information.

February. 1982 Important licensing considerations associated with refueling, e.g., new or 6.

different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

None identified to date J

The number of fuel assemblics (a) in the core and (b) in the spent fuel 7.

storage pool.

,44 - Spent Fuel Assemblies (a) 177 (b) 8 - New Fuel Assemblics The present liaensed spent fuel pool storage capacity and the size of any 8.

incretse in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

Present 735 Increase size by 0 (zero) can le' discharged to the spent 9.

The projected date of the last refueling that fuel pool assuming the present licensed capacity.

fuel 19BC - assuming ability to unload the entire oore into the spent Date pool is maintained

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