ML20138M594: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:. o OPERATING DATA REPORT
{{#Wiki_filter:o OPERATING DATA REPORT DOCKET NO.
* DOCKET NO. 50-247 DATE   12-5-85 COMPLETED BY   K. Krieger TELEPHONE 914-526-5155 OPERATING STATUS Indian Point Unit #2                                     Notes
50-247 DATE 12-5-85 COMPLETED BY K. Krieger TELEPHONE 914-526-5155 OPERATING STATUS Indian Point Unit #2 Notes
: 1. Unit Name:
: 1. Unit Name:
For the year to date, gross
November 1985 For the year to date, gross
: 2. Reporting Period: November 1985 2758                                electrical generation has
: 2. Reporting Period:
: 3. Licensed Thermal Power (MWt):                                           exceeded that for the pre-
: 3. Licensed Thermal Power (MWt):
      '4. Nameplate Rating (Gross MWe):       1013 vious record full year (1983)
2758 electrical generation has 1013 exceeded that for the pre-
: 5. Design Electrical Rating (Net MWe):873
'4. Nameplate Rating (Gross MWe):
: 6. Maximum Dependable Capacity (Gross MWe): 900
vious record full year (1983)
: 7. Maximum Dependable Capacity (Net MWe):         864
: 5. Design Electrical Rating (Net MWe):873 900
: 6. Maximum Dependable Capacity (Gross MWe):
864
: 7. Maximum 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:
None
None
: 9. Power Level To Which Restricted,If Any (Net MWe): None
: 9. Power Level To Which Restricted,If Any (Net MWe): None
: 10. Reasons For Restrictions,if Any:                       No ne This Month             Yr.-to-Date       Cumulative 720                       8016           100105
: 10. Reasons For Restrictions,if Any:
: 11. Hours In Reporting Period
No ne This Month Yr.-to-Date Cumulative 720 8016 100105
: 12. Number Of Hours Reactor Was Critical                 720                    7787.36          68453.08
: 11. Hours In Reporting Period 720 7787.36 68453.08
: 13. Reactor Reserve Shutdown Hours                       0                       152.67           3398.37
: 12. Number Of Hours Reactor Was Critical
: 14. Hours Generator On-Line                               720                     7677.41           AAA?7 ni
: 13. Reactor Reserve Shutdown Hours 0
: 15. Unit Reserve Shutdown Hours                           0                       0                 n
152.67 3398.37
: 16. Gross Thermal Energy Generated (MWH)                 1855601                 20181onn         1799nsus     -
: 14. Hours Generator On-Line 720 7677.41 AAA?7 ni
: 17. Gross Electrical Energy Generated (MWH)               572230          _,
: 15. Unit Reserve Shutdown Hours 0
6322110          53630726
0 n
: 18. Net Electrical Energy Generated (MWH)               550751                  6077638          51191545
: 16. Gross Thermal Energy Generated (MWH) 1855601 20181onn 1799nsus 572230 6322110 53630726
: 19. Unit Service Factor                                   100                     95.8             '66.4
: 17. Gross Electrical Energy Generated (MWH) 550751 6077638 51191545
: 20. Unit Availability Factor                             100                      95.8              66.4
: 18. Net Electrical Energy Generated (MWH)
: 21. Unit Capacity Factor (Using MDC Net)                 88,5                     88.6             59.5
: 19. Unit Service Factor 100 95.8
: 22. Unit Capacity Factor (Using DER Net)                 87.6                    86.8              58.6
'66.4 100 95.8 66.4
: 23. Unit Forced Outage Rate                             0                       3.4               o.n
: 20. Unit Availability Factor
: 21. Unit Capacity Factor (Using MDC Net) 88,5 88.6 59.5 87.6 86.8 58.6
: 22. Unit Capacity Factor (Using DER Net)
: 23. Unit Forced Outage Rate 0
3.4 o.n
: 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
: 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
Cycle 7/8 Refueling and Maintenance Outare, scheduled for 1-15-86 nnd n f n 60 day duration
Cycle 7/8 Refueling and Maintenance Outare, scheduled for 1-15-86 nnd n f n 60 day duration
/A
: 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:
                                                                                      /A
: 26. Units in Test Status (Prior to Commercial Operation):
: 26. Units in Test Status (Prior to Commercial Operation):                         Forecast           Achieved
Forecast Achieved
  ~
~
INITIAL CRITICALITY INITIAL ELECTRICITY                                            /     N/A       [
INITIAL CRITICALITY
COMMERCIAL OPERATION                                         /                 /
/
B512230055 851130 7
N/A
                                                                                        /               /          <hS y-DR ADOCK 0500
[
INITIAL ELECTRICITY COMMERCIAL OPERATION
/
/
/
/
<hS B512230055 851130 y-DR ADOCK 0500 7


AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.         50-247 UNIT       IP #2 DATE 12-5-85 E
AVERAGE DAILY UNIT POWER LEVEL 50-247 DOCKET NO.
UNIT IP #2 12-5-85 DATE E
COMPLETED BY
COMPLETED BY
                                                                                                                          ~
~
TELEPHONE November 1985                                           .
TELEPHONE November 1985 MONTH f
MONTH                                                                                                               f DAY     AVERAGE DAILY POWER LEVEL                           DAY       AVERAGE DAILY POWER LEVEL (MWe-Net)                                                 1MWe-Net) y                   840                                    g7                   548 841                                                           805 2                                                            g 3                   844                                                           838 19 4                    844                                                           833 20 5
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1MWe-Net) 840 548 y
843                                                          748 21 6
g7 2
845                                                          718 22 7
841 805 g
839                                                          836 23 643                                                           841 8                                                           24 827                                                           838 9                                                           25 10                    834                                                           209 26 gg 824                                                           146.
3 844 838 19 844 833 4
27 0lI 12                                                           28 797 804                                                           835 13                                                           29 818 g4 30                     834 827                                                           -
20 843 748 5
15                                                           31                                         _
21 845 718 6
16                   838 l
22 839 836 7
INSTRUCTIONS On this format, list the aserage daily unit power level in MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.
23 643 841 8
l (9/77) ,
24 827 838 9
1 L
25 834 209 10 26 824 146.
gg 27 0lI 797 12 28 804 835 13 29 818 834 g4 30 827 15 31 16 838 INSTRUCTIONS On this format, list the aserage daily unit power level in MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.
(9/77)
L


v       .-
v
                          '?
'?
        ;) ..
;)..
SU MARY OF OPERATING EXPERIENCE
SU MARY OF OPERATING EXPERIENCE
                , November 1985 Unit No. 2 operated at 100% reactor power until Friday, November 8,1985, when load .was reduced to approximately 200 We to facilitate visual
, November 1985 Unit No. 2 operated at 100% reactor power until Friday, November 8,1985, when load.was reduced to approximately 200 We to facilitate visual
                  . verification of.a suspected reactor coolant leak at the gasketed cover plate joint on check valve 897D. This particular valve is in the
. verification of.a suspected reactor coolant leak at the gasketed cover plate joint on check valve 897D. This particular valve is in the
                  ' discharge line tram No.'24 Safety Injection System Accumulator and is located immediately off the loop cold leg. After confirmation that the
' discharge line tram No.'24 Safety Injection System Accumulator and is located immediately off the loop cold leg. After confirmation that the
                  <1eak was at the gasketed joint, load was returned to full power conditions.
<1eak was at the gasketed joint, load was returned to full power conditions.
With the following exceptions, the unit operated at full load for the remainder of the month:
With the following exceptions, the unit operated at full load for the remainder of the month:
o  On November 12th reactor power was reduced to 90% as a result of higher than normal Steam Generator Chlorides. Power was returned to 100% on November 13th.
On November 12th reactor power was reduced to 90% as a result of o
c,--       s o On November 17th reactor power was reduced to 64% to allow the cleaning of the tubes'in #23 Condenser.
higher than normal Steam Generator Chlorides.
Power was returned to 100% on November 13th.
c,--
s o On November 17th reactor power was reduced to 64% to allow the cleaning of the tubes'in #23 Condenser.
f 1
f 1
k'
k'


o On November 21st reactor power was reduced to 74% to allow                                                         -
o On November 21st reactor power was reduced to 74% to allow shutdown of 22 MBFP (Main Boiler Feed Pump) to replace a leaking.
shutdown of 22 MBFP (Main Boiler Feed Pump) to replace a leaking.
hose in the high pressure control oil system. Power was returned s
s  hose in the high pressure control oil system. Power was returned to 100% on November 22nd.
to 100% on November 22nd.
o  On November 26th reactor power was reduced to 15% to reduce radiation fields within containment to allow verification of qualified electrical equipment. Power was returned to 100% on November 28th.
On November 26th reactor power was reduced to 15% to reduce o
                                    , . , , , _ . e , < , . . . .m.~,,. , . - - . . - , ,s.. _ _ . . . , .- -- ..m._ -.- - . , _,,
radiation fields within containment to allow verification of qualified electrical equipment. Power was returned to 100% on November 28th.
e
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,s..
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U 50-247 DOCKET NO.
U 50-247 DOCKET NO.
UNITSHUTDOWNS AND POWER REDUCTIONS                                               IP #2 UNIT NAME DATE       19 4 95 November 1985                 COMPLETED BY           v vh a ea >-
UNITSHUTDOWNS AND POWER REDUCTIONS UNIT NAME IP #2 DATE 19 4 95 November 1985 COMPLETED BY v vh a ea >-
REPORT MONTH                                     TELEPHONE           914-990siss
REPORT MONTH TELEPHONE 914-990siss 5
_    5                                E
E
                    -        .{ g       3   j .E h         Licensee       ,Eg         .                Cause & Corrective No.         Date     g       'd g       %  yss             Event         g7       {"?
.{ g 3
gU                        Action to H
j.E h Licensee
f5         5   j;gg           Report 2r. mo         g                   Prevent Recurrence d5 N/A       85 11 08     S         0       H     N/A         N/A           SD     Valvex B   Controlled load reduction to verify source of increased RCS leakage N/A       85 11 17     S         0       H     N/A         N/A           HC     IITexch D   Condenser cleaning N/A       85 11 26     S         0       B     N/A         N/A           IE     SLECON     Controlled load reduction to facilitat         2 verification of qualified electrical 8"
,Eg
                                                                                              ' equipment within vapor containment 85 11 27                                                                             building i                 2                                                     3                               4 F: Forced         Reason:                                               Method:                           Exhibit G - Instructions S: Scheduled       A-Equipment Failure (Explain)                           1-Manual                         for Preparation of Data B-Maintenance of Test                                 2-Manual Scram.                   Entry Sheets for Licensee C-Refueling                                           3-Automatic Scram.               Event Report (LER) File (NUREG-D-Regulatory Restriction                             4-Other (Explain)                 0161)
{"?
E-Operator Training & License Examination F-Adininistrative                                                                   5 G-Operational Error (Explain)                                                           Exhibit I - Same Source 19/77)               II-Ott er (Explain)
Cause & Corrective No.
Date g
'd g yss Event g7 Action to gU Prevent Recurrence f5 5
j;gg Report 2r.
mo H
g d5 N/A 85 11 08 S
0 H
N/A N/A SD Valvex B Controlled load reduction to verify source of increased RCS leakage N/A 85 11 17 S
0 H
N/A N/A HC IITexch D Condenser cleaning N/A 85 11 26 S
0 B
N/A N/A IE SLECON Controlled load reduction to facilitat 2 verification of qualified electrical 8"
' equipment within vapor containment 85 11 27 building i
2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Adininistrative 5
G-Operational Error (Explain)
Exhibit I - Same Source 19/77)
II-Ott er (Explain)
:~
MAJOR SAFEIT-RELATED CORRECTIVE MAINTENANCE November 1985 WR NO.
SYSTEM COMPONENT DATE WORK PEPSORMED 23042 RVLIS Level Transmitters 11/27/85 Replaced existing LT-1311, 1312, 1321 transmitters with 1322 qualified transmitters 20278-ELEC Terminal Blocks, 11/30/85 Replaced terminal "T" Drains, blocks with qual-Terminal Box ified blocks, Seals and' Drains Installed "T" Drains on valve motor operators and installed terminal block box cover seals and drains 5


:~  .
s-J:hn D. O'Toob
MAJOR SAFEIT-RELATED CORRECTIVE MAINTENANCE November 1985 WR NO.      SYSTEM COMPONENT              DATE    WORK PEPSORMED 23042      RVLIS  Level Transmitters      11/27/85 Replaced existing LT-1311, 1312, 1321              transmitters with 1322                            qualified transmitters 20278-      ELEC  Terminal Blocks,        11/30/85 Replaced terminal "T" Drains,                      blocks with qual-Terminal Box                    ified blocks, Seals and' Drains                Installed "T" Drains on valve motor operators and installed terminal block box cover seals and drains 5
%ce Presx1ent Consolidated Ed: son Company of New Ycrk. loc.
 
4 Irying Piace, New York, NY 10003 Telephone (212) 460 2533 December 16, 1985 Re:
s-
Indian Point Unit No. 2 Docket No. 50-247 Mr. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.-C. 20555 ATIN:
  *-              J:hn D. O'Toob
Document Control Desk
                    %ce Presx1ent Consolidated Ed: son Company of New Ycrk. loc.
4 Irying Piace, New York, NY 10003 Telephone (212) 460 2533 December 16, 1985 Re: Indian Point Unit No. 2 Docket No. 50-247 Mr. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.-C. 20555 ATIN:   Document Control Desk


==Dear Sir:==
==Dear Sir:==
Enclosed are twelve copies of the Monthly Operatirg Report for Indian Point Unit No. 2 for the month of November 1985.
Enclosed are twelve copies of the Monthly Operatirg Report for Indian Point Unit No. 2 for the month of November 1985.
Ver[ truly youys, jL         ,        ff(C_
Ver[ truly youys, jL ff(C_
Encl.
Encl.
cc:     Dr. Thomas E. Murley, Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.             19406 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 38 Buchanan, New York 10511
cc:
Dr. Thomas E. Murley, Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.
19406 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 38 Buchanan, New York 10511
?
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(                                                                                 . _ _ _ _ _ _ _ - - _ - _ _ _ - _ - _ _ - _ - _ _ _ _ _ -}}
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Latest revision as of 18:43, 11 December 2024

Monthly Operating Rept for Nov 1985
ML20138M594
Person / Time
Site: Indian Point 
Issue date: 11/30/1985
From: Krieger K, Otoole J
CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To: Taylor J
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8512230055
Download: ML20138M594 (7)
v • d • e


Text

o OPERATING DATA REPORT DOCKET NO.

50-247 DATE 12-5-85 COMPLETED BY K. Krieger TELEPHONE 914-526-5155 OPERATING STATUS Indian Point Unit #2 Notes

1. Unit Name:

November 1985 For the year to date, gross

2. Reporting Period:
3. Licensed Thermal Power (MWt):

2758 electrical generation has 1013 exceeded that for the pre-

'4. Nameplate Rating (Gross MWe):

vious record full year (1983)

5. Design Electrical Rating (Net MWe):873 900
6. Maximum Dependable Capacity (Gross MWe):

864

7. Maximum Dependable Capacity (Net MWe):
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

None

9. Power Level To Which Restricted,If Any (Net MWe): None
10. Reasons For Restrictions,if Any:

No ne This Month Yr.-to-Date Cumulative 720 8016 100105

11. Hours In Reporting Period 720 7787.36 68453.08
12. Number Of Hours Reactor Was Critical
13. Reactor Reserve Shutdown Hours 0

152.67 3398.37

14. Hours Generator On-Line 720 7677.41 AAA?7 ni
15. Unit Reserve Shutdown Hours 0

0 n

16. Gross Thermal Energy Generated (MWH) 1855601 20181onn 1799nsus 572230 6322110 53630726
17. Gross Electrical Energy Generated (MWH) 550751 6077638 51191545
18. Net Electrical Energy Generated (MWH)
19. Unit Service Factor 100 95.8

'66.4 100 95.8 66.4

20. Unit Availability Factor
21. Unit Capacity Factor (Using MDC Net) 88,5 88.6 59.5 87.6 86.8 58.6
22. Unit Capacity Factor (Using DER Net)
23. Unit Forced Outage Rate 0

3.4 o.n

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):

Cycle 7/8 Refueling and Maintenance Outare, scheduled for 1-15-86 nnd n f n 60 day duration

/A

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

/

N/A

[

INITIAL ELECTRICITY COMMERCIAL OPERATION

/

/

/

/

<hS B512230055 851130 y-DR ADOCK 0500 7

AVERAGE DAILY UNIT POWER LEVEL 50-247 DOCKET NO.

UNIT IP #2 12-5-85 DATE E

COMPLETED BY

~

TELEPHONE November 1985 MONTH f

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1MWe-Net) 840 548 y

g7 2

841 805 g

3 844 838 19 844 833 4

20 843 748 5

21 845 718 6

22 839 836 7

23 643 841 8

24 827 838 9

25 834 209 10 26 824 146.

gg 27 0lI 797 12 28 804 835 13 29 818 834 g4 30 827 15 31 16 838 INSTRUCTIONS On this format, list the aserage daily unit power level in MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.

(9/77)

L

v

'?

)..

SU MARY OF OPERATING EXPERIENCE

, November 1985 Unit No. 2 operated at 100% reactor power until Friday, November 8,1985, when load.was reduced to approximately 200 We to facilitate visual

. verification of.a suspected reactor coolant leak at the gasketed cover plate joint on check valve 897D. This particular valve is in the

' discharge line tram No.'24 Safety Injection System Accumulator and is located immediately off the loop cold leg. After confirmation that the

<1eak was at the gasketed joint, load was returned to full power conditions.

With the following exceptions, the unit operated at full load for the remainder of the month:

On November 12th reactor power was reduced to 90% as a result of o

higher than normal Steam Generator Chlorides.

Power was returned to 100% on November 13th.

c,--

s o On November 17th reactor power was reduced to 64% to allow the cleaning of the tubes'in #23 Condenser.

f 1

k'

o On November 21st reactor power was reduced to 74% to allow shutdown of 22 MBFP (Main Boiler Feed Pump) to replace a leaking.

hose in the high pressure control oil system. Power was returned s

to 100% on November 22nd.

On November 26th reactor power was reduced to 15% to reduce o

radiation fields within containment to allow verification of qualified electrical equipment. Power was returned to 100% on November 28th.

e

.m.~,,.

,s..

..m._

U 50-247 DOCKET NO.

UNITSHUTDOWNS AND POWER REDUCTIONS UNIT NAME IP #2 DATE 19 4 95 November 1985 COMPLETED BY v vh a ea >-

REPORT MONTH TELEPHONE 914-990siss 5

E

.{ g 3

j.E h Licensee

,Eg

{"?

Cause & Corrective No.

Date g

'd g yss Event g7 Action to gU Prevent Recurrence f5 5

j;gg Report 2r.

mo H

g d5 N/A 85 11 08 S

0 H

N/A N/A SD Valvex B Controlled load reduction to verify source of increased RCS leakage N/A 85 11 17 S

0 H

N/A N/A HC IITexch D Condenser cleaning N/A 85 11 26 S

0 B

N/A N/A IE SLECON Controlled load reduction to facilitat 2 verification of qualified electrical 8"

' equipment within vapor containment 85 11 27 building i

2 3

4 F: Forced Reason:

Method:

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

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

Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Adininistrative 5

G-Operational Error (Explain)

Exhibit I - Same Source 19/77)

II-Ott er (Explain)

~

MAJOR SAFEIT-RELATED CORRECTIVE MAINTENANCE November 1985 WR NO.

SYSTEM COMPONENT DATE WORK PEPSORMED 23042 RVLIS Level Transmitters 11/27/85 Replaced existing LT-1311, 1312, 1321 transmitters with 1322 qualified transmitters 20278-ELEC Terminal Blocks, 11/30/85 Replaced terminal "T" Drains, blocks with qual-Terminal Box ified blocks, Seals and' Drains Installed "T" Drains on valve motor operators and installed terminal block box cover seals and drains 5

s-J:hn D. O'Toob

%ce Presx1ent Consolidated Ed: son Company of New Ycrk. loc.

4 Irying Piace, New York, NY 10003 Telephone (212) 460 2533 December 16, 1985 Re:

Indian Point Unit No. 2 Docket No. 50-247 Mr. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.-C. 20555 ATIN:

Document Control Desk

Dear Sir:

Enclosed are twelve copies of the Monthly Operatirg Report for Indian Point Unit No. 2 for the month of November 1985.

Ver[ truly youys, jL ff(C_

Encl.

cc:

Dr. Thomas E. Murley, Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.

19406 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 38 Buchanan, New York 10511

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