ML20101E566: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 17: Line 17:
=Text=
=Text=
{{#Wiki_filter:.
{{#Wiki_filter:.
  . . i.
i.
New Hampshire Y.             k(h                                                                   Ted C. Feigenbovm President and Ch el Executive Of ficer NYN 92078 June 12,1992 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:         Document Control Desk
New Hampshire Y.
k(h Ted C. Feigenbovm President and Ch el Executive Of ficer NYN 92078 June 12,1992 United States Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Document Control Desk


==Reference:==
==Reference:==
Faci.lity Operating License No hi t -o6, Docket No. 50-443 S ubject:           Monthly Operating Report Gentlemen:
Faci.lity Operating License No hi t -o6, Docket No. 50-443 S ubject:
Enclosed please find Monthly Operating Report 92 05. 'Ihis report addresses the operating and sliutdown experience relating to 5cabrook Station U nit I for the month of M a y, 1992 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.
Monthly Operating Report Gentlemen:
Very truly yours, Ted C. Feigen >aum Enclosure cc:       Mr.Thomat T. Martin Regional Administrator U'nited States Nuclear Regalatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Pr oject Directorate 1-3 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senior Resident inspector P.O. Box 1149                                                                                       r Seabrook, NH 03874 9206240035 920531                                                                                                 !
Enclosed please find Monthly Operating Report 92 05.
PDR       ADOOK 05000443                                                                               L   II R                         PDR New Hampshire Yankee Division of Public Semice Company of New Hampshire             /
'Ihis report addresses the operating and sliutdown experience relating to 5cabrook Station U nit I for the month of M a y, 1992 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.
                                                                                                                      / -
Very truly yours, Ted C. Feigen >aum Enclosure cc:
i
Mr.Thomat T. Martin Regional Administrator U'nited States Nuclear Regalatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Pr oject Directorate 1-3 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senior Resident inspector P.O. Box 1149 r
                                                                                                                            '    !' l!
Seabrook, NH 03874 9206240035 920531 PDR ADOOK 05000443 L
p   . , , , ,
II
          .t J b, b , . a             P.O. Box 300
!' l R
* Seabrook, NH 03874 = Telephone (603) 474-9521                     L             I
PDR
'                                                                                                                                    l
/
                        -                                                                                                            1
i New Hampshire Yankee Division of Public Semice Company of New Hampshire
/
p
.t J b, b,. a P.O. Box 300
* Seabrook, NH 03874 = Telephone (603) 474-9521 L
1


                .              - .- -            .      .-      .~   . - - . - - - . - _ . . -                                          .-__                              -, . . - .~.
.~
OPERATING DATA REPORT-                                                                                                               -
-,.. -.~.
DOCKET NO.                       50-443 UNIT Seabrook 1 DATE- 06/12/92-COMPLETED BY P. Nardone TELEPHONE _(603) 474-9521 (Ext. 4074)
OPERATING DATA REPORT-DOCKET NO.
                                                                                                                                                                                                            -i z
50-443 UNIT Seabrook 1 DATE- 06/12/92-COMPLETED BY P.
OPERATING STATUS
Nardone TELEPHONE _(603) 474-9521 (Ext. 4074)
: 1.   ' Unit 1Name;                                   Seabrook Station Unit 1-
-i z
: 2.     Reporting Period:                         -MAY-                                               1992
OPERATING STATUS 1.
: 3.   ' Licensed Thermal Power (MWt):                                                                   3411
' Unit 1Name; Seabrook Station Unit 1-2.
                    . 4.     Nameplate Rating (Gross MWe):                                                                 .1197
Reporting Period:
: 5.     Design Electric           Rating (Net MWe):                                                   1148
-MAY-1992 3.
: 6.     Maximum Dependable Capacity (Gross MWe):                                                       1200                                                                           .
' Licensed Thermal Power (MWt):
: 7.      Maximum Dependable Capacity (Net MWe):                                                         1150                                                                           i
3411
: 8.       If Changes Occur in Capacity Ratings (Items Number 3 Through 7) 1 Since Last--Report, Give Reasons:                                       Not Applicable                                                                                         +
. 4.
: 9.     Power-Level'To Which Restricted. If Any:                                                               None 10.. Reasons For Restricti~ons, If Any:                                               Not Applicable This Month.                       Yr.-to-Date                           Cumulative
Nameplate Rating (Gross MWe):
: 11. hours In Reporting Period                                                               744.0                             3647.0                         49296.0
.1197 5.
: 12. Number of Hours Reactor Was Critical                                                     744.0                             3647.0                         16012.5
Design Electric Rating (Net MWe):
: 13. Reactor Reserve Shutdown Hours                                                             0.0                                         0.0                   953.3             i
1148 6.
!                        14. Hours Generator.On-Line                                                                 744.0                             3647,0                         14171.0 l                     f15. Unit Reserve Shutdown Hours                                                                 0.0                                         0.0                     0.0 16; Gross Thermal Energy Generated (MWH)                                                 2537326                     12433447                             45503307
Maximum Dependable Capacity (Gross MWe):
: 17. Gross Elec. Energy Generated (MWH)                                                     888047                       4350444                           15721693
1200 7.
;-                      18. Net Electrical Energy Generated -(FSG)                                                 854635                       4183917                           15092292                 ;
Maximum Dependable Capacity (Net MWe):
[                   *19. Unit' Service Factor"                                                                       100.0                                 100.0                         81.9
1150 i
                    -*20.-Unit l Availability Factor                                                                 100.0                                 100.0                         81.9
8.
                  '*21. Unit-Capacity Factor (Using MDC Net)                                                         99.9-                                   99.8-                     78.2
If Changes Occur in Capacity Ratings (Items Number 3 Through 7)
                    *22- Unit Capacity Factor (Using DER Net)
Since Last--Report, Give Reasons:
                          .                                                                                          100.1                                     99.9                       78.3
Not Applicable
: l.                   *23. Unit Forced Outage Rate                                                                       0.0                                         0.0                   6.3
+
1 9.
Power-Level'To Which Restricted. If Any:
None 10.. Reasons For Restricti~ons, If Any:
Not Applicable This Month.
Yr.-to-Date Cumulative
: 11. hours In Reporting Period 744.0 3647.0 49296.0
: 12. Number of Hours Reactor Was Critical 744.0 3647.0 16012.5
: 13. Reactor Reserve Shutdown Hours 0.0 0.0 953.3 i
: 14. Hours Generator.On-Line 744.0 3647,0 14171.0 l
f15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 16; Gross Thermal Energy Generated (MWH) 2537326 12433447 45503307
: 17. Gross Elec. Energy Generated (MWH) 888047 4350444 15721693
: 18. Net Electrical Energy Generated -(FSG) 854635 4183917 15092292
[
*19. Unit' Service Factor" 100.0 100.0 81.9
-*20.-Unit l Availability Factor 100.0 100.0 81.9
'*21. Unit-Capacity Factor (Using MDC Net) 99.9-99.8-78.2
*22-Unit Capacity Factor (Using DER Net) 100.1 99.9 78.3 l.
*23. Unit Forced Outage Rate 0.0 0.0 6.3
: 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):
REFUELING, 09/07/92. 59 DAYS l                       25. If Shut Dasci At End Of Report Period. Estimated Date Of Startup: Not Anolicable                                                                                               +
REFUELING, 09/07/92. 59 DAYS l
: 25. If Shut Dasci At End Of Report Period. Estimated Date Of Startup: Not Anolicable
+
t
t
* NOTE: " Cumulative" values based on total hours starting 08/19/90, date Regular Full Power Operation began.
* NOTE: " Cumulative" values based on total hours starting 08/19/90, date Regular Full Power Operation began.
i 1 of 4 i
i 1 of 4 i
      ,v,_-.     ..-y     y           --_ - _ ,  . . _ _ _ . ,    . . _      . . . . . . - . , . . . . . . , - ,          . . , -  ,,,.,,,._..,.._...__.m-,-.-.-..                       .~...w,----
,v,_-.
..-y y
,,,.,,,._..,.._...__.m-,-.-.-..
.~...w,----


AVERAGE DAILY UNIT POWER-LEVEL DOCKET NO.     50-443 UNIT Seabrook I' DATE   06/12/92 COHPLETED BY -P. Nardcne TELEPHONE (603) 474-9521 (Ext. 4074)
AVERAGE DAILY UNIT POWER-LEVEL DOCKET NO.
MONTH     MAY.'1992 i
50-443 UNIT Seabrook I' DATE 06/12/92 COHPLETED BY
DAY'   AVERAGE DAILY POWER LEVEL                               DAY   AVERAGE DAILY POWER LEVEL
-P.
                              . (KJe.Ne t ) .                                                   (MWe-Net) 1               1150                                           16               1148 2               1150                                           17               1149 3               1150                                           18               1149 4               1150                                           19               1149
Nardcne TELEPHONE (603) 474-9521 (Ext. 4074)
                .5               1149                                           20               1150 t
MONTH MAY.'1992 i
6               1149-                                         21               1150 I
DAY' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
7               1149                                           22               1150 i
. (KJe.Ne t ).
8               1149                                           23               1249
(MWe-Net) 1 1150 16 1148 2
[               9               1149                                           24               1148 10               1149                                           25               1147 l.
1150 17 1149 3
l               -- 11           -1150                                           26               1147 12               1150                                           27               1146 i
1150 18 1149 4
13     _
1150 19 1149
1148                                           28               1147 i                14               1149                                           29               1148 l:
.5 1149 20 1150 t
15               1148                                           30               1147
6 1149-21 1150 I
,                                                                                31               1149 INSTRUCTIONS
7 1149 22 1150 i
                .On this format, list the average daily unit power level in MWe-Net f or each day in the report-ing month.         Compute to the nearest whole megawatt.
8 1149 23 1249
: l.                                                               2 of 4 i
[
9 1149 24 1148 10 1149 25 1147 l.
l
-- 11
-1150 26 1147 12 1150 27 1146 i
13 1148 28 1147 14 1149 29 1148 i
l:
15 1148 30 1147 31 1149 INSTRUCTIONS
.On this format, list the average daily unit power level in MWe-Net f or each day in the report-ing month.
Compute to the nearest whole megawatt.
l.
2 of 4 i
t
t


UNIT SHUTDOWNS AND POWER REDUCTIONS                         DOCKET NO. 50-443                 ;
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT Seabrook 1               ,
50-443 UNIT Seabrook 1 DATE 06/12/92 REPORT MONTH _ MAY. 1942 COMroETED BY P. Nardone TELEPHONE (603) 474-952i (Ext. 4074)
DATE   06/12/92 COMroETED BY  P. Nardone REPORT MONTH _ MAY. 1942 TELEPHONE (603) 474-952i (Ext. 4074)
No.
Method of         Licensee             Cause & Corrective No. Date  Type l     Duration    Reason?
Date Type Duration Reason?
Shutting           Event                   Action to (Hours)
Method of Licensee Cause & Corrective l
Down Reactor 3
(Hours)
Report i             Prevent Recurrence Page 1 of 1 NO ENTRIES FOR THIS MONTH 3
Shutting Event Action to Down Reactor Report i Prevent Recurrence 3
1                     2 Method:
Page 1 of 1 NO ENTRIES FOR THIS MONTH 3
F   Forced             Reason:
1 2
A-Equipment Failure (Explain)                               1-Manual S:  Scheduled B-Maintenance or Test                                       2-Manual Scran C-Refueling                                                  3-Automatic Stran D-Regulatory Restriction                                    4-Continued from E-Operator Training & License Examination                     previous month F-Administrative                                            5-Power Reduction G-Operational Error (Explain)                                 (Duration = 0)
Method:
H-Other (Explain)                                           9-Other ("xplain) 3 of 4
F Forced Reason:
S:
Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scran 3-Automatic Stran C-Refueling 4-Continued from D-Regulatory Restriction E-Operator Training & License Examination previous month 5-Power Reduction F-Administrative G-Operational Error (Explain)
(Duration = 0) 9-Other ("xplain)
H-Other (Explain) 3 of 4


    ,  -                  . . . . . . - ..                  -~,       .            -- . - . - - . - . - - . -              .      .              .        _          . - - .      . - - - --
-~,
      .'A. ,
.'A.
DOCKET NO                         50-443                               ,
DOCKET NO 50-443 UNIT Seabrook 1 DATE 06/12/92 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)
                        ,                                                                                                        UNIT Seabrook 1 DATE                     06/12/92
* COMPLETED BY                   P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)
REFUELING-INFORMATION REQUEST
REFUELING-INFORMATION REQUEST
: 1. Name of facility:                     Seabrook Unit 1
: 1. Name of facility:
: 2. Scheduled date for next refueling shutdown:                                                       09/07/92 9
Seabrook Unit 1
: 2. Scheduled date for next refueling shutdown:
09/07/92 9
3.. Scheduled date for restart following refueling:
3.. Scheduled date for restart following refueling:
11/04/92
11/04/92
: 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
: 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes, Reactor Coolant System Narrow Range RTD Bypass Elimination
Yes, Reactor Coolant System Narrow Range RTD Bypass Elimination 5.
: 5. Scheduled date(s) for submitting licensing action and supporting information:
Scheduled date(s) for submitting licensing action and supporting information:
.                                March 15, 1992 6.' Important licensing consideratfans 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:
March 15, 1992 6.' Important licensing consideratfans 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:
Next refueling will be the initial start of the eighteen-month fuel cycle schedule.
Next refueling will be the initial start of the eighteen-month fuel cycle schedule.
i             7-. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage
i 7-.
                  -pool:
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage
[                                 (a)         In Core:     193                                                   (b)     60
-pool:
: 8. The present licensed spent fuel pool storage capacity and the size of any                                                                                                         i increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
[
4 Present licensed capacity: 1?36
(a)
,                                No increase in storage capacity requested or planned.
In Core:
4 3.
193 (b) 60
          - 9. The. projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:                                                                                                                                   t Licensed capacity of 1236 fuel assemblies based on two annual and twelve eighteen-month refuelings with full core offload capability, t.
: 8. The present licensed spent fuel pool storage capacity and the size of any i
increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
4 Present licensed capacity:
1?36 No increase in storage capacity requested or planned.
3.
4
- 9. The. projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
t Licensed capacity of 1236 fuel assemblies based on two annual and twelve eighteen-month refuelings with full core offload capability, t.
The current licensed capacity is adequate until at least the year 2010.
The current licensed capacity is adequate until at least the year 2010.
l 4 of 4 a
l 4 of 4 a
  . 4           --_ ,,                  _
4
                                                            ,          -, . _ _ . - - . . _ ~ , . _ . _ _ . _ . .               _ _ , . . _ . - , - - , . . _ . , - - _ - - . - . , -}}
-,. _ _. - -.. _ ~,. _. _ _. _..
_ _,.. _. -, - -,.. _., - - _ - -. -., -}}

Latest revision as of 05:03, 13 December 2024

Monthly Operating Rept for May 1992 for Seabrook Station Unit 1
ML20101E566
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 05/31/1992
From: Feigenbaum T, Nardone P
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NYN-92078, NUDOCS 9206240035
Download: ML20101E566 (5)


Text

.

i.

New Hampshire Y.

k(h Ted C. Feigenbovm President and Ch el Executive Of ficer NYN 92078 June 12,1992 United States Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Document Control Desk

Reference:

Faci.lity Operating License No hi t -o6, Docket No. 50-443 S ubject:

Monthly Operating Report Gentlemen:

Enclosed please find Monthly Operating Report 92 05.

'Ihis report addresses the operating and sliutdown experience relating to 5cabrook Station U nit I for the month of M a y, 1992 and is submitted in accordance with the requirements of Seabrook Station Technical Specification 6.8.1.5.

Very truly yours, Ted C. Feigen >aum Enclosure cc:

Mr.Thomat T. Martin Regional Administrator U'nited States Nuclear Regalatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Pr oject Directorate 1-3 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Noel Dudley NRC Senior Resident inspector P.O. Box 1149 r

Seabrook, NH 03874 9206240035 920531 PDR ADOOK 05000443 L

II

!' l R

PDR

/

i New Hampshire Yankee Division of Public Semice Company of New Hampshire

/

p

.t J b, b,. a P.O. Box 300

  • Seabrook, NH 03874 = Telephone (603) 474-9521 L

1

.~

-,.. -.~.

OPERATING DATA REPORT-DOCKET NO.

50-443 UNIT Seabrook 1 DATE- 06/12/92-COMPLETED BY P.

Nardone TELEPHONE _(603) 474-9521 (Ext. 4074)

-i z

OPERATING STATUS 1.

' Unit 1Name; Seabrook Station Unit 1-2.

Reporting Period:

-MAY-1992 3.

' Licensed Thermal Power (MWt):

3411

. 4.

Nameplate Rating (Gross MWe):

.1197 5.

Design Electric Rating (Net MWe):

1148 6.

Maximum Dependable Capacity (Gross MWe):

1200 7.

Maximum Dependable Capacity (Net MWe):

1150 i

8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7)

Since Last--Report, Give Reasons:

Not Applicable

+

1 9.

Power-Level'To Which Restricted. If Any:

None 10.. Reasons For Restricti~ons, If Any:

Not Applicable This Month.

Yr.-to-Date Cumulative

11. hours In Reporting Period 744.0 3647.0 49296.0
12. Number of Hours Reactor Was Critical 744.0 3647.0 16012.5
13. Reactor Reserve Shutdown Hours 0.0 0.0 953.3 i
14. Hours Generator.On-Line 744.0 3647,0 14171.0 l

f15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 16; Gross Thermal Energy Generated (MWH) 2537326 12433447 45503307

17. Gross Elec. Energy Generated (MWH) 888047 4350444 15721693
18. Net Electrical Energy Generated -(FSG) 854635 4183917 15092292

[

  • 19. Unit' Service Factor" 100.0 100.0 81.9

-*20.-Unit l Availability Factor 100.0 100.0 81.9

'*21. Unit-Capacity Factor (Using MDC Net) 99.9-99.8-78.2

  • 22-Unit Capacity Factor (Using DER Net) 100.1 99.9 78.3 l.
  • 23. Unit Forced Outage Rate 0.0 0.0 6.3
24. Shutdowns Scheduled-Over Next 6 Months (Type, Date, and Duration of Each):

REFUELING, 09/07/92. 59 DAYS l

25. If Shut Dasci At End Of Report Period. Estimated Date Of Startup: Not Anolicable

+

t

  • NOTE: " Cumulative" values based on total hours starting 08/19/90, date Regular Full Power Operation began.

i 1 of 4 i

,v,_-.

..-y y

,,,.,,,._..,.._...__.m-,-.-.-..

.~...w,----

AVERAGE DAILY UNIT POWER-LEVEL DOCKET NO.

50-443 UNIT Seabrook I' DATE 06/12/92 COHPLETED BY

-P.

Nardcne TELEPHONE (603) 474-9521 (Ext. 4074)

MONTH MAY.'1992 i

DAY' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

. (KJe.Ne t ).

(MWe-Net) 1 1150 16 1148 2

1150 17 1149 3

1150 18 1149 4

1150 19 1149

.5 1149 20 1150 t

6 1149-21 1150 I

7 1149 22 1150 i

8 1149 23 1249

[

9 1149 24 1148 10 1149 25 1147 l.

l

-- 11

-1150 26 1147 12 1150 27 1146 i

13 1148 28 1147 14 1149 29 1148 i

l:

15 1148 30 1147 31 1149 INSTRUCTIONS

.On this format, list the average daily unit power level in MWe-Net f or each day in the report-ing month.

Compute to the nearest whole megawatt.

l.

2 of 4 i

t

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-443 UNIT Seabrook 1 DATE 06/12/92 REPORT MONTH _ MAY. 1942 COMroETED BY P. Nardone TELEPHONE (603) 474-952i (Ext. 4074)

No.

Date Type Duration Reason?

Method of Licensee Cause & Corrective l

(Hours)

Shutting Event Action to Down Reactor Report i Prevent Recurrence 3

Page 1 of 1 NO ENTRIES FOR THIS MONTH 3

1 2

Method:

F Forced Reason:

S:

Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scran 3-Automatic Stran C-Refueling 4-Continued from D-Regulatory Restriction E-Operator Training & License Examination previous month 5-Power Reduction F-Administrative G-Operational Error (Explain)

(Duration = 0) 9-Other ("xplain)

H-Other (Explain) 3 of 4

-~,

.'A.

DOCKET NO 50-443 UNIT Seabrook 1 DATE 06/12/92 COMPLETED BY P. Nardone TELEPHONE (603) 474-9521 (Ext. 4074)

REFUELING-INFORMATION REQUEST

1. Name of facility:

Seabrook Unit 1

2. Scheduled date for next refueling shutdown:

09/07/92 9

3.. Scheduled date for restart following refueling:

11/04/92

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

Yes, Reactor Coolant System Narrow Range RTD Bypass Elimination 5.

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

March 15, 1992 6.' Important licensing consideratfans 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:

Next refueling will be the initial start of the eighteen-month fuel cycle schedule.

i 7-.

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

-pool:

[

(a)

In Core:

193 (b) 60

8. The present licensed spent fuel pool storage capacity and the size of any i

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

4 Present licensed capacity:

1?36 No increase in storage capacity requested or planned.

3.

4

- 9. The. projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

t Licensed capacity of 1236 fuel assemblies based on two annual and twelve eighteen-month refuelings with full core offload capability, t.

The current licensed capacity is adequate until at least the year 2010.

l 4 of 4 a

4

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

_ _,.. _. -, - -,.. _., - - _ - -. -., -