ML20195F982: Difference between revisions

From kanterella
Jump to navigation Jump to search
← Older edit
VisualWikitext
StriderTol Bot change
StriderTol Bot change
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:_ _.               .      - . . _ _ . . . _ . . _        .  ... __-      . ~ . _ _ . _ . . _ _ _ _ . . . _ _ . - _ ~ . _ _ _ _ _ . _ _ _ . _ _
{{#Wiki_filter:_ _.
l t ..      .
. ~. _ _. _.. _ _ _ _... _ _. - _ ~. _ _ _ _ _. _ _ _. _ _
U.S. Nuclear Regulatory Commission B17459%ttrehment 1\P g)1 i
l t
REFUELING INFORMATION REQUEST l                                                           October 1998 l
U.S. Nuclear Regulatory Commission B17459%ttrehment 1\\P g)1 i
l
REFUELING INFORMATION REQUEST l
: 1. Name of the facility:               Millstone Unit 3
October 1998 l
: 2. Scheduled date for next refueling outage: May 15.1999
l 1.
: 3. Scheduled date for restart following refueling: .Julv 5.1999
Name of the facility:
: 4. Will refueling or resumption of operation thereafter require a technical t                specification change or other license amendment?
Millstone Unit 3 2.
Yes - Full Core Offload.
Scheduled date for next refueling outage: May 15.1999 3.
: 5.   . Scheduled date(s) for submitting licensing betion and supporting information:
Scheduled date for restart following refueling:.Julv 5.1999 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
t Yes - Full Core Offload.
5.
. Scheduled date(s) for submitting licensing betion and supporting information:
Full Core Offload - 12/98.
Full Core Offload - 12/98.
l
l 6.
: 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
None.
None.
j          7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage                                                         j pool:
7.
1 In Core: '(a)               193               In Spent Fuel Pool: (b) 416                                                     ,
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage j
: 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
j pool:
1 In Core: '(a) 193 In Spent Fuel Pool: (b) 416 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
Erg.spnt storaae caoacity: 756.
Erg.spnt storaae caoacity: 756.
                -Increase in licensed storage caoacity olanned for total of 1860 locations.
-Increase in licensed storage caoacity olanned for total of 1860 locations.
9.. The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
9..
The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
End of Cvcle 7.
End of Cvcle 7.
l t
l t
i 9811200145 981112 S PDR     ADOCK 05000423 R                               pop
i 9811200145 981112 S PDR ADOCK 05000423 R
pop


                                                                                                  .. ~ - -   - . ~ . . -
.. ~ - -
          *        . s
-. ~.. -
    ;  U.S. Nuclear Regulatory Commission B17450%ttachment1\P g)2 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 50-423 UNIT: Millstone Unit 3 DATE:   11/9/98 COMPLETED BY:         K.W. Emmons TELEPHONE:     (860) 447-1791 Ext. 6572 MONTH: Oct-98 DAY       AVG DAILY POWER LEVEL                             DAY         AVG. DAILY POWER LEVEL (MWe-Net)                                                 (MWe-Net) 1                     1096                                 17                   1149 2                       611                                 18                   1147 3                       1116                                 19                   1150 4                       1145                                 20                     1152 5                       1146                                 21                     1149 6                       1148                                 22                     1144 7                       1152                                 23                     1151 8                       1103                                 24                     1151 9                       1108                                 25                     1145 10                     1097                                 26                     1139 11                     1022                                 27                     1140 12                       973                                 28                     420 13                     1004                                 29                       0 14                       982                                 30                       0 15                     1137                                 31                       0 16                     1145 l
. s U.S. Nuclear Regulatory Commission B17450%ttachment1\\P g)2 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 50-423 UNIT: Millstone Unit 3 DATE:
l     ' INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each 2
11/9/98 COMPLETED BY:
      - day in the reporting month. Compute to the nearest whole megawatt.
K.W. Emmons TELEPHONE:
J 4
(860) 447-1791 Ext. 6572 MONTH: Oct-98 DAY AVG DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1096 17 1149 2
611 18 1147 3
1116 19 1150 4
1145 20 1152 5
1146 21 1149 6
1148 22 1144 7
1152 23 1151 8
1103 24 1151 9
1108 25 1145 10 1097 26 1139 11 1022 27 1140 12 973 28 420 13 1004 29 0
14 982 30 0
15 1137 31 0
16 1145 l
l
' INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each
- day in the reporting month. Compute to the nearest whole megawatt.
2 J
4 i
 
^
U.S. Nuclear Regul;t:ry C:mmissi:n l
B17459%tt:chment 1\\P:g3 3 I
l OPERATING DATA REPORT UNIT NAME:
Millstone Unit 3 DATE:
11/09/98 COMPLETED BY:
K. W. Emmons TELEPHONE:
(860)447-1791 Ext 6572 OPERATING STATUS 1.
Docket Number 50-423 2.
Reporting Period Oct 98 Notes:
i
i
 
: 3. Utihty Contact K. W. Emmons 4.
      ^
Licensed Thermal Power (MWt):
  ; U.S. Nuclear Regul;t:ry C:mmissi:n l  B17459%tt:chment 1\P:g3 3 I
3411 5.
l                                              OPERATING DATA REPORT                                                                              l UNIT NAME:                    Millstone Unit 3  l DATE:        11/09/98          l COMPLETED BY:                    K. W. Emmons TELEPHONE:                  (860)447-1791 Ext 6572 OPERATING STATUS
Nameplate Rating (Gross MWe):
: 1. Docket Number                                            50-423
1253 6.
: 2. Reporting Period                                          Oct 98                        Notes:                                          i
Design Electrical Rating (Net MWe):
: 3. Utihty Contact                                               K. W. Emmons                                                                   l
1153.6 7.
: 4. Licensed Thermal Power (MWt):                                     3411                                                                     l
Maximum Dependable Capacity (Gross MWe):
: 5. Nameplate Rating (Gross MWe):                                     1253
1184.2 8.
: 6. Design Electrical Rating (Net MWe):                             1153.6
Maximum Dependable Capacity (Net MWe):
: 7. Maximum Dependable Capacity (Gross MWe):                         1184.2
1137.0
: 8. Maximum Dependable Capacity (Net MWe):                           1137.0                                                                     ,
: 9. If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, Give Reasons:
: 9. If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report,                                                         l Give Reasons:                                                                                                                           I N/A
N/A
: 10. Power Level To Which Restricted, If any (Net Mwe): N/A
: 10. Power Level To Which Restricted, If any (Net Mwe): N/A
: 11. Reasons For Restrictions,if Any:                 N/A This Month       Yr.-To-Date                     Cumulative
: 11. Reasons For Restrictions,if Any:
: 12. Hours in Reporting Period                                                       745.0                   7296.0               109800.0, 13 Number Of Hours Reactor Was Critical                                             692.0                   2701.1                 69781.2
N/A This Month Yr.-To-Date Cumulative
: 14. Reactor Reserve Shutdown Hours                                                     0.0                               0.0           6525.8
: 12. Hours in Reporting Period 745.0 7296.0 109800.0, 13 Number Of Hours Reactor Was Critical 692.0 2701.1 69781.2
: 15. Hours Generator On-Line                                                         661.3                   2505.1                 68417.5
: 14. Reactor Reserve Shutdown Hours 0.0 0.0 6525.8
: 16. Unit Reserve Shutdown Hours                                                       0.0                               0.0               0.0
: 15. Hours Generator On-Line 661.3 2505.1 68417.5
: 17. Gross Thermal Energy Generated (MWH)                                         2173356.0         7826886.0                   224764614.1   )
: 16. Unit Reserve Shutdown Hours 0.0 0.0 0.0
: 18. Gross Electrical Energy Generated (MWH)                                       753919.5         2675007.0                   77580110.1
: 17. Gross Thermal Energy Generated (MWH) 2173356.0 7826886.0 224764614.1
: 19. Net Electrical Energy Generated (MWH)                                         719079.1         2454018.1                   73692327.4
)
: 20. Unit Service Factor                                                               88.8                           34.3               62.3
: 18. Gross Electrical Energy Generated (MWH) 753919.5 2675007.0 77580110.1
: 21. Unit Availability Factor                                                         88.8                           34.3               62.3
: 19. Net Electrical Energy Generated (MWH) 719079.1 2454018.1 73692327.4
: 22. Unit Capacity Factor (Using MDC Net)                                             84.9                           29.6               59.0
: 20. Unit Service Factor 88.8 34.3 62.3
: 23. Unit Capacity Factor (Using DER Net)                                             83.7                           29.2               58.2
: 21. Unit Availability Factor 88.8 34.3 62.3
: 24. Unit Forced Outage Rate                                                           11.2                           65.5               30.8
: 22. Unit Capacity Factor (Using MDC Net) 84.9 29.6 59.0
: 25. Unit Forced Outage Hours                                                         83.7                   4764.2                 30490.3 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):                 N/A
: 23. Unit Capacity Factor (Using DER Net) 83.7 29.2 58.2
: 27. If Currently Shutdown, Estimated Date of Startup:                                             N/A l   28. Units in Test Status (Prior to Commercial Operation):
: 24. Unit Forced Outage Rate 11.2 65.5 30.8
l                                                                                                       Forecest                     Achieved j                                                    INITIAL CRITICAUTY                                       N/A                       N/A
: 25. Unit Forced Outage Hours 83.7 4764.2 30490.3 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
;                                                    INITIAL ELECTRICITY                                       N/A                       N/A COMMERCIAL OPERATION                                     N/A                       N/A i
N/A
: 27. If Currently Shutdown, Estimated Date of Startup:
N/A l
: 28. Units in Test Status (Prior to Commercial Operation):
l Forecest Achieved INITIAL CRITICAUTY N/A N/A j
INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A i


;              U.S. Nuclear Regulatory Commission                                                                                                                                                                                                                                                                                                                                                 .
U.S. Nuclear Regulatory Commission G17459%ttachment 1Page 4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.:
G17459%ttachment 1Page 4 UNIT SHUTDOWNS AND POWER REDUCTIONS                                                                                                                                                                                                         $
50-423 UNIT NAME:
DOCKET NO.:                 50-423 UNIT NAME:             Millstone Unit 3           *
Millstone Unit 3 DATE:
,                                                                                                                                                                                                                                                                                                                                                    DATE:             11X)9/98 COMPLETED BY:                         K. W. Emmons ~
11X)9/98 COMPLETED BY:
TELEPHONE:               1860) 447-1791 X6572 REPORT MONTH: October 1998 No.         Date                           Type'               Duration                                       Reason
K. W. Emmons ~
* Method of                                                     License                                       System                                       Componmd Cause & Corrective (Hours)                                                                         Shutting                                                     Event                                         Code'                                         Code
TELEPHONE:
* Actum to
1860) 447-1791 X6572 REPORT MONTH: October 1998 No.
.,                                                                                                                                                              Down Reactor
Date Type' Duration Reason
* Report #                                                                                                                       Prevent Recurrence 98-06 10-01-98                                     F               O                                             A                                         5                                               98-039                                               EF                                                     . INVT       Reduced power to 48% due to blown fuse in inverter.
* Method of License System Componmd Cause & Corrective (Hours)
Shutting Event Code' Code
* Actum to Down Reactor
* Report #
Prevent Recurrence 98-06 10-01-98 F
O A
5 98-039 EF
. INVT Reduced power to 48% due to blown fuse in inverter.
Replaced cwcurt cards associated with the *F1* fuse.
Replaced cwcurt cards associated with the *F1* fuse.
98-07 10-28-98                                     F               83.7                                           A                                         2                                                             -
98-07 10-28-98 F
SH                                                         COND ' Manual plant trip due to high condensate conductivity.
83.7 A
2 SH COND ' Manual plant trip due to high condensate conductivity.
Water entered system throug5 cracked tube in *C*
Water entered system throug5 cracked tube in *C*
condenser waterbox.
condenser waterbox.
                'F: Forced                                             Reason                                                                                                                                   ' Method                                                                                                                             'IEEE Standard 805-1984, S: Scheduled                                           A - Equipment Failure (Explain)                                                                                                                 1 - Manual                                                                                                                       " Recommended Practices B - Maintenance or Test                                                                                                                       2 - Manual Scram                                                                                                                 for System identrficatum in i                                                                     C - Refueling .                                                                                                                               3 - Automatic Scram                                                                                                               Nuclear Power Plants and D - Regulatory Restriction                                                                                                                     4 - Continued from Previous Month                                                                                                 Related Facilities
'F: Forced
* E - Operator Training & License Examination                                                                                                   5 - Power Reduction (Duration = 0)
#Reason
F - Administrative                                                                                                                             6 - Other (Explain)                                                                                                           .* IEEE Standard 803A-1983, G - Operational Error (Explain)                                                                                                                                                                                                                                                 " Recommended Practices l                                                                       H - Other (Explain)                                                                                                                                                                                                                                                             for Uneque identification in Power Plants and Related Facilities - Component Function identifiers"
' Method
'IEEE Standard 805-1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual
" Recommended Practices B - Maintenance or Test 2 - Manual Scram for System identrficatum in i
C - Refueling.
3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities
* E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)
F - Administrative 6 - Other (Explain)
. IEEE Standard 803A-1983, G - Operational Error (Explain)
" Recommended Practices l
H - Other (Explain) for Uneque identification in Power Plants and Related Facilities - Component Function identifiers"
)
)
___.__...___.___.___._.____m_        -
m m.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -                                                                                  _m._                                                        _ . _ .        ,r
,r


a     -
a Docket No. 50-423 B17459 i
Docket No. 50-423 B17459 Attachment 2                                    i Millstone Nuclear Power Station, Unit No. 3                     1 l
Millstone Nuclear Power Station, Unit No. 3 1
Revised Page " Average Daily Unit Power Level"                   i Month of September                                   l l
Revised Page " Average Daily Unit Power Level" Month of September i
i i
i I
I
November 1998 i
!                                                                      November 1998 i
i
i
  . -}}
. -}}

Latest revision as of 18:38, 10 December 2024

Monthly Operating Rept for Oct 1998 for Millstone,Unit 3
ML20195F982
Person / Time
Site: Millstone 
Issue date: 10/31/1998
From: Emmons K
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20195F919 List:
References
NUDOCS 9811200145
Download: ML20195F982 (5)
v • d • e


Text

_ _.

. ~. _ _. _.. _ _ _ _... _ _. - _ ~. _ _ _ _ _. _ _ _. _ _

l t

U.S. Nuclear Regulatory Commission B17459%ttrehment 1\\P g)1 i

REFUELING INFORMATION REQUEST l

October 1998 l

l 1.

Name of the facility:

Millstone Unit 3 2.

Scheduled date for next refueling outage: May 15.1999 3.

Scheduled date for restart following refueling:.Julv 5.1999 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

t Yes - Full Core Offload.

5.

. Scheduled date(s) for submitting licensing betion and supporting information:

Full Core Offload - 12/98.

l 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

None.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage j

j pool:

1 In Core: '(a) 193 In Spent Fuel Pool: (b) 416 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

Erg.spnt storaae caoacity: 756.

-Increase in licensed storage caoacity olanned for total of 1860 locations.

9..

The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:

End of Cvcle 7.

l t

i 9811200145 981112 S PDR ADOCK 05000423 R

pop

.. ~ - -

-. ~.. -

. s U.S. Nuclear Regulatory Commission B17450%ttachment1\\P g)2 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 50-423 UNIT: Millstone Unit 3 DATE:

11/9/98 COMPLETED BY:

K.W. Emmons TELEPHONE:

(860) 447-1791 Ext. 6572 MONTH: Oct-98 DAY AVG DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1096 17 1149 2

611 18 1147 3

1116 19 1150 4

1145 20 1152 5

1146 21 1149 6

1148 22 1144 7

1152 23 1151 8

1103 24 1151 9

1108 25 1145 10 1097 26 1139 11 1022 27 1140 12 973 28 420 13 1004 29 0

14 982 30 0

15 1137 31 0

16 1145 l

l

' INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each

- day in the reporting month. Compute to the nearest whole megawatt.

2 J

4 i

^

U.S. Nuclear Regul;t:ry C:mmissi:n l

B17459%tt:chment 1\\P:g3 3 I

l OPERATING DATA REPORT UNIT NAME:

Millstone Unit 3 DATE:

11/09/98 COMPLETED BY:

K. W. Emmons TELEPHONE:

(860)447-1791 Ext 6572 OPERATING STATUS 1.

Docket Number 50-423 2.

Reporting Period Oct 98 Notes:

i

3. Utihty Contact K. W. Emmons 4.

Licensed Thermal Power (MWt):

3411 5.

Nameplate Rating (Gross MWe):

1253 6.

Design Electrical Rating (Net MWe):

1153.6 7.

Maximum Dependable Capacity (Gross MWe):

1184.2 8.

Maximum Dependable Capacity (Net MWe):

1137.0

9. If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report, Give Reasons:

N/A

10. Power Level To Which Restricted, If any (Net Mwe): N/A
11. Reasons For Restrictions,if Any:

N/A This Month Yr.-To-Date Cumulative

12. Hours in Reporting Period 745.0 7296.0 109800.0, 13 Number Of Hours Reactor Was Critical 692.0 2701.1 69781.2
14. Reactor Reserve Shutdown Hours 0.0 0.0 6525.8
15. Hours Generator On-Line 661.3 2505.1 68417.5
16. Unit Reserve Shutdown Hours 0.0 0.0 0.0
17. Gross Thermal Energy Generated (MWH) 2173356.0 7826886.0 224764614.1

)

18. Gross Electrical Energy Generated (MWH) 753919.5 2675007.0 77580110.1
19. Net Electrical Energy Generated (MWH) 719079.1 2454018.1 73692327.4
20. Unit Service Factor 88.8 34.3 62.3
21. Unit Availability Factor 88.8 34.3 62.3
22. Unit Capacity Factor (Using MDC Net) 84.9 29.6 59.0
23. Unit Capacity Factor (Using DER Net) 83.7 29.2 58.2
24. Unit Forced Outage Rate 11.2 65.5 30.8
25. Unit Forced Outage Hours 83.7 4764.2 30490.3 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

N/A

27. If Currently Shutdown, Estimated Date of Startup:

N/A l

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

l Forecest Achieved INITIAL CRITICAUTY N/A N/A j

INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A i

U.S. Nuclear Regulatory Commission G17459%ttachment 1Page 4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.:

50-423 UNIT NAME:

Millstone Unit 3 DATE:

11X)9/98 COMPLETED BY:

K. W. Emmons ~

TELEPHONE:

1860) 447-1791 X6572 REPORT MONTH: October 1998 No.

Date Type' Duration Reason

  • Method of License System Componmd Cause & Corrective (Hours)

Shutting Event Code' Code

  • Actum to Down Reactor
  • Report #

Prevent Recurrence 98-06 10-01-98 F

O A

5 98-039 EF

. INVT Reduced power to 48% due to blown fuse in inverter.

Replaced cwcurt cards associated with the *F1* fuse.

98-07 10-28-98 F

83.7 A

2 SH COND ' Manual plant trip due to high condensate conductivity.

Water entered system throug5 cracked tube in *C*

condenser waterbox.

'F: Forced

  1. Reason

' Method

'IEEE Standard 805-1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual

" Recommended Practices B - Maintenance or Test 2 - Manual Scram for System identrficatum in i

C - Refueling.

3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities

  • E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)

F - Administrative 6 - Other (Explain)

. IEEE Standard 803A-1983, G - Operational Error (Explain)

" Recommended Practices l

H - Other (Explain) for Uneque identification in Power Plants and Related Facilities - Component Function identifiers"

)

m m.

,r

a Docket No. 50-423 B17459 i

Millstone Nuclear Power Station, Unit No. 3 1

Revised Page " Average Daily Unit Power Level" Month of September i

i I

November 1998 i

i

. -

Retrieved from "https://kanterella.com/w/index.php?title=ML20195F982&oldid=4119892"