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=Text=
=Text=
{{#Wiki_filter:Corald R. Asiney Vice Presiderit Peach Bottom Atomic Power Station -         l
{{#Wiki_filter:Corald R. Asiney Vice Presiderit Peach Bottom Atomic Power Station -
.-        -.,                                                                                                                    a
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PECO ENERGY                                                                 R ggc--                                     !
Delta. PA 17314-9739 717 456 7014
Delta. PA 17314-9739 717 456 7014                                 ;
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                                                                                                                                    'i l
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January 12,1994 U.S. Nuclear Regulatory Commission Document Control Desk                                                                                               -3 Washington, D.C. 20555                                                                                                 j Docket Nos 50-277 and 50-278                                                                               ,
January 12,1994 U.S. Nuclear Regulatory Commission Document Control Desk
Gentlemen:
-3 Washington, D.C. 20555 j
i Enclosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and                     -l 3 for the month of December 1993 forwarded pursuant to Technical Specification 6.9.1.d under the                     .,
Docket Nos 50-277 and 50-278 Gentlemen:
guidance of Regulatory Guide 10.1, Revision 4.                                                                         l Sincerely,                                                                                                           .l
i Enclosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and
                                -                                                                                                  l
-l 3 for the month of December 1993 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.
            // k Gerald R. Rainey                                                                                                       :
l Sincerely,
Vice President -                                                                                                       I a! I!()//(>r[
.l l
GRR/AJW/GHG/TJN/MSH:wjj l
// k Gerald R. Rainey Vice President -
l enclosures                                                                                                             .
I a! I!()//(>r[
f cc:     R.A. Burricelli, Public Service Electric'& Gas                                                                 i W.P. Dornsife, Commonwealth of Pennsylvania                                                                   l R.I. McLean, State of Maryland                                                                             -l T.T. Martin, Administrator, Region I, USNRC                                                                 -l -
l GRR/AJW/GHG/TJN/MSH:wjj l
W.L Schmidt, USNRC, Senior Resident Inspector H.C. Schwemm, Atlantic Electric                                                                               ;
enclosures f
C.D. Schaefer Delmarva Power INPO Records Center                                                                                           i t
cc:
R.A. Burricelli, Public Service Electric'& Gas i
W.P. Dornsife, Commonwealth of Pennsylvania l
R.I. McLean, State of Maryland
-l T.T. Martin, Administrator, Region I, USNRC
-l W.L Schmidt, USNRC, Senior Resident Inspector H.C. Schwemm, Atlantic Electric C.D. Schaefer Delmarva Power INPO Records Center i
t
:l I
:l I
                                                                                                                                  'f i     A ccn #94-14003                                                                                   .-            )
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I a                                                                                                             l PEACH BOTTOM ATOMIC POWER STATION NRC MONTHLY OPERATIONS  
I a
PEACH BOTTOM ATOMIC POWER STATION NRC MONTHLY OPERATIONS  


==SUMMARY==
==SUMMARY==
 
DECEMBER 1993 OVERVIEW OF ACTIVITIES
DECEMBER 1993 OVERVIEW OF ACTIVITIES                                                         ,
_q0MMON PLART The following plant maintenance outages occurred during the month of December.
_q0MMON PLART The following plant maintenance outages occurred during the month of December.                           l l
* Diesel Driven Fire Pump UNIT 2
* Diesel Driven Fire Pump l
'l l
UNIT 2                                                                                                   ,
                                                                                                                'l l
Unit 2 began the month of December at a nominal 100% power.
Unit 2 began the month of December at a nominal 100% power.
I On December 10,1993 at 04:00 hours power was reduced to perform control rod stroking. The unit was       I returned to 100% power at 0600 hours.
I On December 10,1993 at 04:00 hours power was reduced to perform control rod stroking. The unit was returned to 100% power at 0600 hours.
On December 18,1993 at 01:00 hours power was reduced to 60% to perform maintenance on the "2B" reactor feed pump and perform rod pattern adjustments.
On December 18,1993 at 01:00 hours power was reduced to 60% to perform maintenance on the "2B" reactor feed pump and perform rod pattern adjustments.
On December 19,1993 at 18:00 hours the unit was returned to 100% nominal power.
On December 19,1993 at 18:00 hours the unit was returned to 100% nominal power.
On December 31,1993 at 01:00 hours power was reduced to perform Turbine Stop Valve testing. The unit was returned to 100% nominal power at 04:00 hours.
On December 31,1993 at 01:00 hours power was reduced to perform Turbine Stop Valve testing. The unit was returned to 100% nominal power at 04:00 hours.
The following maintenance outages occurred on Unit 2:
The following maintenance outages occurred on Unit 2:
                  * *B" Loop RHR
* *B" Loop RHR
* E3 Diesel
* E3 Diesel
* Turbine Building Ventilation Heating Coils                                                   ,
* Turbine Building Ventilation Heating Coils i
i 1
1 UNIT 3 Unit 3 began the month of December at a nominal 100% power.
UNIT 3                                                                                                 ,
Unit 3 began the month of December at a nominal 100% power.                                           ,
On December 1,1993 at 22:00 hours the unit was shutdown. This was due to RHR MO-2-10-25A being inoperable.
On December 1,1993 at 22:00 hours the unit was shutdown. This was due to RHR MO-2-10-25A being inoperable.
On December 15,1993 at 21:00 hours the Unit 3 outage ended when the main generator was synchronized   ,
On December 15,1993 at 21:00 hours the Unit 3 outage ended when the main generator was synchronized to the grid.
to the grid.                                                                                       .i On December 171993 at 21:00 hours Unit 3 reached 100% power.                                         j On December 29,1993 at 21:00 hours power was reduced due to a recirc pump runback on 'A' pump. The   ,
.i On December 171993 at 21:00 hours Unit 3 reached 100% power.
unit was returned to 100% nominal power at 00:00 hours on December 30,1993.
j On December 29,1993 at 21:00 hours power was reduced due to a recirc pump runback on 'A' pump. The unit was returned to 100% nominal power at 00:00 hours on December 30,1993.
Unit 3 ended the month at 100% nominal power.                                                         !
Unit 3 ended the month at 100% nominal power.
The following maintenance outages occured on Unit 3:
The following maintenance outages occured on Unit 3:
* Turbine Building Ventilation Heating Coils
* Turbine Building Ventilation Heating Coils
* Reactor Building Closed Cooling Water
* Reactor Building Closed Cooling Water


        ._                            -            -                            ~ ,.        .-        -                  ..
~,.
      .                                                                                                                          t Docket No. 50-277 J                                                                                                     Attachment to
t Docket No. 50-277 J
                                                                                                  - Monthly Operating Report for December 1993 l
Attachment to
UNIT 2 REFUEUNG INFORMATION                                                 .
- Monthly Operating Report for December 1993 l
: 1. Name of facility:
UNIT 2 REFUEUNG INFORMATION 1.
* Peach 30ttom Unit 2
Name of facility:
: 2. Scheduled date for next refueling shutdown:
Peach 30ttom Unit 2 2.
Reload 10 scheduled for September 10,1994.                                                            .
Scheduled date for next refueling shutdown:
Reload 10 scheduled for September 10,1994.
E i
E i
: 3. Scheduled date for restart following refueling:
3.
Scheduled date for restart following refueling:
Restart following refueling forecast for December 8,1994.
Restart following refueling forecast for December 8,1994.
: 4. Will refueling or resumption of operation therefore require a technical specification change or other license amendment?                                                                                             l No.                                                                                                     i if answer is yes, what, in general, will these be?
4.
: 5. Scheduled date(s) for submitting proposed licensing action and supporting information:
Will refueling or resumption of operation therefore require a technical specification change or other license amendment?
N/A                                                                                                 .
l No.
i
i if answer is yes, what, in general, will these be?
: 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or '
5.
supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:                                                                                         I 1
Scheduled date(s) for submitting proposed licensing action and supporting information:
N/A i
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:
I 1
N/A i
N/A i
I
I 7.
: 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) Core - 764 Fuel Assemblies (b) Fuel Pool - 2164 Fuel Assemblies,58 Fuel Rods                                                       I
(a) Core - 764 Fuel Assemblies (b) Fuel Pool - 2164 Fuel Assemblies,58 Fuel Rods 8.
: 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:
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:
The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies, l
The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies,


Docket No. 50-277 Attachment to Monthly Operating Report for December 1993           ,
Docket No. 50-277 Attachment to Monthly Operating Report for December 1993 Page 2 UNIT 2 REFQELING INFORMATipe (Continued) 9.
                                                                                                  -            Page 2 UNIT 2 REFQELING INFORMATipe (Continued)                                               '
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity:
: 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity:
P September 2003 without full core offload capability.
P September 2003 without full core offload capability.
September 1997 with full core offload capability.
September 1997 with full core offload capability.
Line 106: Line 116:
i k
i k
b b
b b
w ..                         -            -        .-                                                      ,      , ~ .
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, ~.


                        . _,_              - .-              .  - -~             .                  .    - - .          .      - -- ,
- -~
i
i l
          *.                                                                                                                                  l Docket 12o. 50-278             .
Docket 12o. 50-278 Attachment to.
l Attachment to .                 i Monthly Operating                   i I
i Monthly Operating i
Report for December 1993 l
Report for December 1993 UNIT 3 REFUELING INFORMATION l
UNIT 3 REFUELING INFORMATION                                                             <
1.
l
Name of facility:
: 1. Name of facility:                                                                                                   -
Peach Bottom Unit 3 i
Peach Bottom Unit 3                                                                                         i i
i 2.
: 2. Scheduled date for next refueling shutdown:                                                                           !
Scheduled date for next refueling shutdown:
t Reload 10 scheduled for September 11,1995                                                                   j
t Reload 10 scheduled for September 11,1995 j
: 3. Scheduled date for restart following refueling                                                                     '!  ,
3.
Restart following refueling scheduled for November 13,1995
Scheduled date for restart following refueling Restart following refueling scheduled for November 13,1995 4.
: 4. Will refueling or resumption of operation thereafter require a technical specification change or other                 .
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
license amendment?                                                                                                     !
No if answer is yes, what, in general, will these be?
No if answer is yes, what, in general, will these be?
5   Scheduled date(s) for submitting proposed licensing action and supporting information:
5 Scheduled date(s) for submitting proposed licensing action and supporting information:
i N/A
i N/A 6.
: 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or                     i supplier, unreviewed design or performance analysis methods, significant changes in fuel design,                         l new operating procedures:
Important licensing considerations associated with refueling, e.g., new or different fuel design or i
N/A
supplier, unreviewed design or performance analysis methods, significant changes in fuel design, l
: 7. The nurnber of fuel assemblies (a) in the ' core and (b) in the spent fuel storage pool:
new operating procedures:
(a)     Core - 764 Fuel AssemNies (b)     Fuel Pool - 2201 Fuel Assemblies,6 Fuel Rods                                                         I
N/A 7.
: 8. The present licensed spent fuel pool storage capacity and the size of any increase.in licensed '                         r storage capacity that has been requested or is planned, in number at fuel assemblies:
The nurnber of fuel assemblies (a) in the ' core and (b) in the spent fuel storage pool:
(a)
Core - 764 Fuel AssemNies (b)
Fuel Pool - 2201 Fuel Assemblies,6 Fuel Rods I
8.
The present licensed spent fuel pool storage capacity and the size of any increase.in licensed '
r storage capacity that has been requested or is planned, in number at fuel assemblies:
j The spent fuel pool storage capacity has been reticensed for 3819 fuel assemblies.
j The spent fuel pool storage capacity has been reticensed for 3819 fuel assemblies.
l t
l t
i
i 4.-
                                                                                      .  ,                              #  4.- .


p.
p.
l                                                                                                 Docket No. 50-278
l Docket No. 50-278 Attachment to Monthly Operating i
      .'                                                                                                Attachment to Monthly Operating i                                                                                       Report for December 1993         .,
Report for December 1993 Page 2 l
                                                                                              ..                Page 2       l F                                                                                                                           :
F UNIT 3 REFUELING INFORMATION (Continued) i 9.
UNIT 3 REFUELING INFORMATION (Continued) i
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity:
: 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the   ,      !
  >              present capacity:                                                                                           ;
September 2004 without full core offload capability.
September 2004 without full core offload capability.
September 1998 with full core offload capability.
September 1998 with full core offload capability.
i
i
                                                                                                                            't i
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                                                                                                                            ^!
^
_ _      _  _                                      ._                              ..        .~     _  .
.~


                                        -      . . . .    .-                    -        . -          .  . . . . . .. ~ . .
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        .                                                                                                                      t
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                    .                                                                                                        +
+
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277                                             !
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277 t
t                                                                                                                           .
UNIT PEACH BOTTOM UNIT 2 t
UNIT PEACH BOTTOM UNIT 2                                   t
DATE JkNhkRh kh,hh9k
                                                                                                  ' ^""
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8.-
8.-
DATE JkNhkRh kh,hh9k i
i COMPANY PECO ENERGY COMPANY W. J. JEFFREY r
COMPANY PECO ENERGY COMPANY W. J. JEFFREY                                       r PERFORMANCE & RELIABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027                             I MONTH DECEMBER 1993 DAY AVERAGE DAILY POWER LEVEL               DAY AVERAGE DA!LY POWER LEVEL (MWE-NET )                                 (MWE-NET)                             ?
PERFORMANCE & RELIABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027 I
1                     1D60                 17                 1068 2                   1064                 18                   749 i
MONTH DECEMBER 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DA!LY POWER LEVEL (MWE-NET )
3                     1064                 19                   991 4                     ' D60               20                 1066 5                     1060                 21                 1070 t
(MWE-NET)
6                     1061                 22                 1070 7                     1061                 23                 1053
?
* 8                    1061                 24                 1069 9                   1066                 25                 1069 10                   1061                 26                 1065 l
1 1D60 17 1068 2
11                   1065                 27                 1069                               l 12                   1065                 28                 1065 13                   1064                 29                 1065
1064 18 749 i
3 1064 19 991 4
' D60 20 1066 5
1060 21 1070 t
6 1061 22 1070 7
1061 23 1053 8
1061 24 1069 9
1066 25 1069 10 1061 26 1065 l
11 1065 27 1069 l
12 1065 28 1065 13 1064 29 1065
{
{
14                     1065                 30                 1056 15                     1063                 31                 1044 16                     1071 e
14 1065 30 1056 15 1063 31 1044 16 1071 e
a J
a J
4
4
                                                                                                                                ]
]
Y l
Y i
i 1
l l
l l
                ...    . -            -              .    -~
-~


                                                                                                                                                          ]
]
l 9
l 9
AVERACE DAILY UNIT POWER LEVEL
AVERACE DAILY UNIT POWER LEVEL
                                                                                                      .                                                  )
)
.                                              DOCKET No. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE JANUARY 11,1994 COMPANY PECO ENERGY COMPANY V. J. JEFFREY                                                                                 '
DOCKET No. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE JANUARY 11,1994 COMPANY PECO ENERGY COMPANY V. J. JEFFREY PERFORMANCE & RELIABILITY SITE ENGINEER 161G PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027 I
PERFORMANCE & RELIABILITY SITE ENGINEER 161G PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027 I
MONTH DECEMBER 1993 i
MONTH DECEMBER 1993                                                                                                                           i I
I t
t DAY AVFRAGE DAILY POWER LEVEL                 DAY AVERACE DAILY POWER LEVEL (MWE* NET)                                                                                                                 f (MWE NET)                                                                       i t
DAY AVFRAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL f
1                 1036                     17                   811                                                                     I 2                     80                     18                 1041 3                       0                   19                 1058 4                       0                   20                 1070
(MWE* NET)
                                                                                                                                                          '5 5                       0                   21                 1074 6                       0                   22               1066 i
(MWE NET) i t
7                       0                   23               1057 8                     0                     24               1066 9                     0                   25                 1070 i
1 1036 17 811 I
10                     0                   26                 1061                                                                         i 11                       7                   27                 1069 12                       0                   28                 1065                                                                         1 1
2 80 18 1041 3
13                       0                   29                 1057 i
0 19 1058 4
a 14                       0                   30               1065 15                       6                   31               1061 1
0 20 1070
16                   287                                                                                                                     $
'5 5
0 21 1074 6
0 22 1066 i
7 0
23 1057 8
0 24 1066 9
0 25 1070 i
10 0
26 1061 i
11 7
27 1069 12 0
28 1065 1
1 13 0
29 1057 i
14 0
30 1065 a
15 6
31 1061 1
16 287 i
I I
k I
 
.a 1
i I
i I
I k
OPERATING DATA REPORT l
I
DOCKET NO. 50 - 277 DATE JANUARY 11,1994 COMPLETED BY PECO ENERGY COMPANY'.........
 
W. J. JEFFREY PERFORMANCE & RELIABILITY l
  ,  .a                      . - . - -              - - -                -.                        -              .                                          -.  .
SITE ENGINEERING i
1 i
PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT, 4027
    ,                                                                                                                                                                        I OPERATING DATA REPORT l
- i OPERATING STATUS
DOCKET NO. 50 - 277                                                       l DATE JANUARY 11,1994 COMPLETED               BY PECO ENERGY COMPANY'.........
: 1. UN!T NAME: PEACH BOTTOM UNIT 2 NOTES:
W. J. JEFFREY                                           .I PERFORMANCE & RELIABILITY SITE ENGINEERING l
: 2. REPORTING PERIOD: DECEMBER, 1993
i PEACH BOTTOM ATOMIC POWER STATION                         '
_ j
TELEPHONE (717) 456-7014 EXT, 4027
: 3. LICENSED THERMAL POWER (MWT):
                                                                                                                                                                          -i OPERATING STATUS
3293 l
: 1. UN!T NAME: PEACH BOTTOM UNIT 2                                                                                                                           '
: 4. NAMEPLATE RATING (GROSS MWE):
NOTES:
1152
_j
: 5. DESIGN ELECTRICAL RATING (NET MWE):
: 2. REPORTING PERIOD: DECEMBER, 1993                                                                                                                         '
1065
: 3. LICENSED THERMAL POWER (MWT):                                   3293                                                                                     l
: 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
: 4. NAMEPLATE RATING (GROSS MWE):                                   1152                                                                                     !
: 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
: 5. DESIGN ELECTRICAL RATING (NET MWE):                             1065
1055 l
: 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098                                                                                                             *
: 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):                         1055         l
: 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
: 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
: 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY INET MWE):
: 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY INET MWE):
                                                                                                                                                                            ?
?
: 10. REASONS FOR RESTRICTIONS, IF ANY:
: 10. REASONS FOR RESTRICTIONS, IF ANY:
t THIS MONTH             YR-TO-DATE                     CUMULATIVE
t THIS MONTH YR-TO-DATE CUMULATIVE
: 11. HOURS IN REPORTING PER100                                                               744                   8,760                   170,880         _i
: 11. HOURS IN REPORTING PER100 744 8,760 170,880
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL                                               hk b                   h,hhbb                     bb,h2 .             -
_ i
: 13. REACTOR RESERVE SHUTDOWN HOURS                                                         bb                       bb                         bb
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL hk b h,hhbb bb,h2.
: 14. HOURS GENERATOR ON-LINE                                                           hIkb                 hShk$b                     5bh,hhb$h
: 13. REACTOR RESERVE SHUTDOWN HOURS bb bb bb
: 15. UNIT RESERVE SHUTDOWN HOURS                                                             0.0                     0.0                       0.0
: 14. HOURS GENERATOR ON-LINE hIkb hShk$b 5bh,hhb$h
: 16. GRO$$ THERMAL ENERGY GENERATED (MWH)                                       2,418,406             24,119,749                 3D4,489,493
: 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
: 17. GROSS ELECTRICAL ENERGY GENERATED (MWH)                                       806,200               7,979,100                 100,151,490               i
: 16. GRO$$ THERMAL ENERGY GENERATED (MWH) 2,418,406 24,119,749 3D4,489,493
: 18. NET ELECTRICAL ENERGY GENERATED (MWH)                                         hb5kbh               hTbkbk3                       95,99bbbh PAGE 1 0F 2-k h
: 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 806,200 7,979,100 100,151,490 i
: 18. NET ELECTRICAL ENERGY GENERATED (MWH) hb5kbh hTbkbk3 95,99bbbh PAGE 1 0F 2-k h
t i
t i
                                                                                                                                                                          'h a
' h a
e a


          .                                                                                                                                    ,1
+
              +                                                                                                                                  i t         .
i t
t OPERATING DATA REPORT (CONTINUED) .                                 DOCKET _ NO. 50 - 277 i
t OPERATING DATA REPORT (CONTINUED).
                                                                                        .............................                          l DATE JANUARY 11,1994 THIS MONTH           YR TO-DATE             CUMULATIVE-               6
DOCKET _ NO. 50 - 277 i
: 19. UNIT SERVICE FACTOR                                     100.0                   86.4                   59.8 i               20. UNIT AVAILABILITY FACTOR                                 100.0                   86.4                   59.8
l DATE JANUARY 11,1994 6
: 21. UNIT CAPACITY FACTOR (USING MDC NET)                       99.6                   83.4                   53.2
THIS MONTH YR TO-DATE CUMULATIVE-
: 22. UNIT CAPACITY FACTOR (USING DER NET)                       98.7                   82.6                   52.7             j
: 19. UNIT SERVICE FACTOR 100.0 86.4 59.8 i
: 23. UNIT FORCED DUTAGE RATE b$b 5$5       "''" II5$9
: 20. UNIT AVAILABILITY FACTOR 100.0 86.4 59.8
: 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):                                                 ,
: 21. UNIT CAPACITY FACTOR (USING MDC NET) 99.6 83.4 53.2
                                                                                                                                          'k
: 22. UNIT CAPACITY FACTOR (USING DER NET) 98.7 82.6 52.7 j
: 23. UNIT FORCED DUTAGE RATE b$b 5$5
"''" II5$9
: 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
'k
: 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A
: 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A
: 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):           FORECAST           ACHIEVED                               I JNITIAL CRITICALITY                                             09/16/73                               .
: 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):
INITIAL ELECTRICITY                                             02/18/74 COMMERCIAL OPERATION                                             07/05/74                           -I t
FORECAST ACHIEVED I
JNITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 COMMERCIAL OPERATION 07/05/74
-I t
PAGE 2 0F 2
PAGE 2 0F 2
                                                                                                                                          .3 N
.3'!
7 b
N 7
i i
b i
F i
i F
                                                                                                                                              .t
i
.t


                                                                                                                      ..2 i
..2 i
l
l[.
[.
7 s
7 s
OPERATING DATA REPORT DOCKET No. 50 - 278 DATE JANUARY 11,1994 COMPLETED BY PECO ENERGY COMPANY 7
OPERATING DATA REPORT DOCKET No. 50 - 278 DATE JANUARY 11,1994 COMPLETED BY PECO ENERGY COMPANY 7
W. J. JEFFREY                               ~
W. J. JEFFREY
~
PERFORKANCE & RELIABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027 OPERATING STA1US
PERFORKANCE & RELIABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027 OPERATING STA1US
: 1. UNIT NAME: PEACH BOTTOM UNIT 3                                         NOTES:                                                 ;
: 1. UNIT NAME: PEACH BOTTOM UNIT 3 NOTES:
I
I
: 2. REPORTING PERIOD: DE CEMBER, 1993
: 2. REPORTING PERIOD: DE CEMBER, 1993
: 3. LICENSED THERMAL POWER (MWT):                         3293
: 3. LICENSED THERMAL POWER (MWT):
: 4. NAMEPLATE RATING (GROSS MWE):                           1152 I
3293
: 5. DESIGN ELECTRICAL RATING (NET MWE):                     1065         1
: 4. NAMEPLATE RATING (GROSS MWE):
1152 I
: 5. DESIGN ELECTRICAL RATING (NET MWE):
1065 1
: 6. MAXIMON DEPENDABLE CAPACITY (GROSS MWE): 1098
: 6. MAXIMON DEPENDABLE CAPACITY (GROSS MWE): 1098
                                                                            ~
~
: 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):                 1035
: 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1035
: 8. If CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
: 8. If CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
: 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
: 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
: 10. REASONS FOR RESTRICTIONS, IF ANY:
: 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH         YR-TO-DATE           CUMULATIVE       /
THIS MONTH YR-TO-DATE CUMULATIVE
/
t
t
: 11. HOURS IN REPORTING PER100                                                   744               B,760             166,776       1
: 11. HOURS IN REPORTING PER100 744 B,760 166,776 1
                                                                              ""''~~               ~'"~
""''~~
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL                                     difb             6633b         ~~kb,bfi$E
~'"~
: 13. REACTOR RESERVE SHUTDOWN HOURS                                             0.0                 0.0                 0.0       i
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL difb 6633b
: 14. HOURS GENERATOR ON-LINE                                                   417.0           6,594.0           101,291.2         l
~~kb,bfi$E
: 15. UNIT RESERVE SHU1DOWN HOURS                                                 hh                 bh                   hh
: 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 i
: 16. GRO$$ THERMAL ENERGY GENERATED (MWH)                               1,303,896         20,192,267         298,773,477
: 14. HOURS GENERATOR ON-LINE 417.0 6,594.0 101,291.2 l
: 17. GROSS ELECTRICAL ENERGY GENERATED (MWH)                               423,000           6,550,000         97,990,132           ;
: 15. UNIT RESERVE SHU1DOWN HOURS hh bh hh
                                                                            ............          ............        ............            7
: 16. GRO$$ THERMAL ENERGY GENERATED (MWH) 1,303,896 20,192,267 298,773,477
: 18. NET ELEC1RICAL ENERGY GENERATED (MWH)                                 408,740           6,310,370         93,974,336 PAGE 1 0F 2         j 3
: 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 423,000 6,550,000 97,990,132 7
I i
: 18. NET ELEC1RICAL ENERGY GENERATED (MWH) 408,740 6,310,370 93,974,336 PAGE 1 0F 2 j
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* t OPERATING DATA REPORT (CONTINUED)                                   DOCKET NO. 50 + 278 DATE JANUARY 11,1994                                   I r
OPERATING DATA REPORT (CONTINUED)
THIS MONTH         YR-TO-DATE               CUMULATIVE i
DOCKET NO. 50 + 278 DATE JANUARY 11,1994 I
: 19. UNIT SERVICE FACTOR                                       56.0                 75.3                   60.7
r THIS MONTH YR-TO-DATE CUMULATIVE i
: 19. UNIT SERVICE FACTOR 56.0 75.3 60.7
[
[
: 20. UNIT AVAILABILITY FACTOR                                   56.0                 75.3                   _60.7 t
: 20. UNIT AVAILABILITY FACTOR 56.0 75.3
: 21. UNIT CAPACITY FACTOR (USING MDC NE1)                       53.1                 69.6                     54.4         .
_60.7 t
: 22. UNIT CAPACITY FACTOR (UsihG DER kET)                       51.6                 67.6                     52.9
: 21. UNIT CAPACITY FACTOR (USING MDC NE1) 53.1 69.6 54.4
                                                            ............          ............            ............              1
: 22. UNIT CAPACITY FACTOR (UsihG DER kET) 51.6 67.6 52.9 1
: 23. UNIT FORCED DUTAGE RATE                                   44.0                   6.8                   12.3
: 23. UNIT FORCED DUTAGE RATE 44.0 6.8 12.3
: 24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATIDN OF EACH):                                            :
: 24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATIDN OF EACH):
: 25. IF SHUTDOWN AT END OF REPCRT PER100, ESTIMATED DATE OF STARTUP: 11/14/95
: 25. IF SHUTDOWN AT END OF REPCRT PER100, ESTIMATED DATE OF STARTUP: 11/14/95
: 26. 05:T5 IN TEST STATUS (PRIOR TO COMMERCIAL DPERATION):           FORECAST           ACHIEVED INITIAL CRITICALITY                                             08/07/74                           i INITIAL ELECTRICITY                                             09/01/74
: 26. 05:T5 IN TEST STATUS (PRIOR TO COMMERCIAL DPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 i
INITIAL ELECTRICITY 09/01/74
[
[
COMMERCIAL OPERATION                                           12/23/74                         ,;
COMMERCIAL OPERATION 12/23/74 b
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i UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50 - 277 t
UNIT SHUTDOWNS AND POWER REDUCTIONS                             DOCKET No. 50 - 277                                 t UNIT NAME PEACH BOTTOM UNIT 2                     {
UNIT NAME PEACH BOTTOM UNIT 2
DATE JANUARY 11,1994 REPORT MONTH DE CEMBER, 1993                             COMPLETED BY PECO ENERGY COMPANY
{
                                                                        ...............                                        .............................          i W. J. JEFFREY PERFORMANCE & RELIABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT, 4027
DATE JANUARY 11,1994 REPORT MONTH DE CEMBER, 1993 COMPLETED BY PECO ENERGY COMPANY i
      .............................................................................................................................                                    i METHOD OF l t!CENSEE jsYSTEMlCOMPONENTj CAUSE AND CORRECTIVE                                             l T1PE DURATION REASON SHUTTING DOWN!                 EVENT     j CODE l CODE l               ACTION TO Wo.         DATE     (1)       (HOURS)     (2)       REAC10R (3) l REPORT # l (4) l               (5) l PREVENT RECURRENCE l
W. J. JEFFREY PERFORMANCE & RELIABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT, 4027 i
t                                                     9         4 26         931210       S1       2.0       B             4               N/A   j RC l CONROD             CONTROL ROO STROKlNG. REACTOR NOT SHUTDOWN I
METHOD OF l t!CENSEE jsYSTEMlCOMPONENTj CAUSE AND CORRECTIVE l
27           931219       F       41.0         B       ,    4               N/A       RC       CONROD       ROD PATTERN ADJUSTMENT AND REACTOR FEED PUMP' l               MAINTENANCE. REACTOR NOT SHUTDOWN I                   !
T1PE DURATION REASON SHUTTING DOWN!
I                   ;
EVENT j CODE l CODE l ACTION TO Wo.
28           931231       Sl'      3.0       B             4               N/A       HE       VALVEX       TURBINE STOP VALVE TESTING.
DATE (1)
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(HOURS)
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REAC10R (3) l REPORT # l (4) l (5) l PREVENT RECURRENCE l
F* FORCED                   REASON                                                     METHOD                         EXHIBIT G . INSTRUCT 10NS S - SCHEDULED               A - EQUIPMENT FAILURE (EXPLAIN)                             1 - MANUAL                       FOR PREPARATION OF DATA                   i B - MAINTENANCE OR TEST                                     2 - MANUAL SCRAM.               ENTRY SHEETS FOR LICENSEE                 i C - REFUELING-                                             3 - AUTOMATIC SCRAM.           EVENT REPORT (LER)
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D - REGULATORY RESTRICTION                                 4 OTHER (EXPLAIN)                 FILE (NUREG-0161)
4 26 931210 S1 2.0 B
E OPERATOR TRAINING + LICENSE EXAMINATION                                                                                             '
4 N/A j RC l CONROD CONTROL ROO STROKlNG. REACTOR NOT SHUTDOWN I
F = ADMINISTRATIVE                                                                                   (5)
27 931219 F
41.0 B
4 N/A RC CONROD ROD PATTERN ADJUSTMENT AND REACTOR FEED PUMP' l
MAINTENANCE. REACTOR NOT SHUTDOWN I
I 28 931231 Sl 3.0 B
4 N/A HE VALVEX TURBINE STOP VALVE TESTING.
REACTOR NOT SHUTDOWN I
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B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE i
C - REFUELING-3 - AUTOMATIC SCRAM.
EVENT REPORT (LER)
D - REGULATORY RESTRICTION 4 OTHER (EXPLAIN)
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E OPERATOR TRAINING + LICENSE EXAMINATION F = ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EKPLAIN)
G - OPERATIONAL ERROR (EKPLAIN)
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L UNIT SHUTDOWNS AND POWER REDUCTIONS                   DOCKET No. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE JANUARY 11,1994
L UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE JANUARY 11,1994 REPORT MONTH DECEMBER,1993 COMPLETED BY PECO ENERGY COMPANY V. J. JEFFREY PERFORMANCE & RELIABILITY i
,                                              REPORT MONTH DECEMBER,1993                   COMPLETED BY PECO ENERGY COMPANY V. J. JEFFREY                                                             <
I SITE ENGINEERING PEACH BOTTOM ATOMIC POWEk STATION I
PERFORMANCE & RELIABILITY                                                 i I
TELEPHONE (717) 456-7014 EXT. 4027 l
SITE ENGINEERING PEACH BOTTOM ATOMIC POWEk STATION                                         I TELEPHONE (717) 456-7014 EXT. 4027                                                     l l         l            METHOD OF l LICENSEE - SYSTEM COMPONENT' CAUSE AND CDRRECTIVE TYPE lDURATIONjREA50Nf'SHUTTINGDOWNj       EVENT       CODE       CODE         ACTION TO No.     DATE   (1)l(HOURS)j (2) l REACTOR (3) l REPORT #               (4)       (5)     PREVENT RECURRENCE
l METHOD OF l LICENSEE - SYSTEM COMPONENT' CAUSE AND CDRRECTIVE TYPE lDURATIONjREA50Nf'SHUTTINGDOWNj EVENT CODE CODE ACTION TO No.
                                    !                                              I        l 25   931201     F     335.0 l       A         1             N/A       SF lVALVEX LPCI MOTOR OPERATED VALVE Mo-25A INOPERABLE i
DATE (1)l(HOURS)j (2) l REACTOR (3) l REPORT #
l 26   931229     F       3.0 j       A         4             N/A       CB     PUMPXX     "A" RECIRC PUMP RUNBACK. REACTOR NOT SHUTDOWN                                       ;
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5 SCHEDULED         A - EQUIPMENT FA! LURE (EXPLAIN)                     1 - MANUAL                   FOR PREPARATION OF DATA                                                     I B - MAINTENANCE OR TEST                             2 - MANUAL SCRAM.           ENTRY SNEETS FOR LICENSEE                                                   ]
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Latest revision as of 22:16, 16 December 2024

Monthly Operating Repts for Dec 1993 for Peach Bottom Units 2 & 3
ML20062N917
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/31/1993
From: Jeffrey W, Rainey G
AFFILIATION NOT ASSIGNED, PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CCN-94-14003, NUDOCS 9401240204
Download: ML20062N917 (14)


Text

Corald R. Asiney Vice Presiderit Peach Bottom Atomic Power Station -

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%.y PECO ENERGY R ggc--

Delta. PA 17314-9739 717 456 7014

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January 12,1994 U.S. Nuclear Regulatory Commission Document Control Desk

-3 Washington, D.C. 20555 j

Docket Nos 50-277 and 50-278 Gentlemen:

i Enclosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and

-l 3 for the month of December 1993 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

l Sincerely,

.l l

// k Gerald R. Rainey Vice President -

I a! I!()//(>r[

l GRR/AJW/GHG/TJN/MSH:wjj l

enclosures f

cc:

R.A. Burricelli, Public Service Electric'& Gas i

W.P. Dornsife, Commonwealth of Pennsylvania l

R.I. McLean, State of Maryland

-l T.T. Martin, Administrator, Region I, USNRC

-l W.L Schmidt, USNRC, Senior Resident Inspector H.C. Schwemm, Atlantic Electric C.D. Schaefer Delmarva Power INPO Records Center i

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A ccn #94-14003

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p-9401240204 931231 r.

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-. _ _, _. P DR '. \\/t. _ - { d PDR ADOCK 05000277P-1 i

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PEACH BOTTOM ATOMIC POWER STATION NRC MONTHLY OPERATIONS

SUMMARY

DECEMBER 1993 OVERVIEW OF ACTIVITIES

_q0MMON PLART The following plant maintenance outages occurred during the month of December.

  • Diesel Driven Fire Pump UNIT 2

'l l

Unit 2 began the month of December at a nominal 100% power.

I On December 10,1993 at 04:00 hours power was reduced to perform control rod stroking. The unit was returned to 100% power at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />.

On December 18,1993 at 01:00 hours power was reduced to 60% to perform maintenance on the "2B" reactor feed pump and perform rod pattern adjustments.

On December 19,1993 at 18:00 hours the unit was returned to 100% nominal power.

On December 31,1993 at 01:00 hours power was reduced to perform Turbine Stop Valve testing. The unit was returned to 100% nominal power at 04:00 hours.

The following maintenance outages occurred on Unit 2:

  • E3 Diesel
  • Turbine Building Ventilation Heating Coils i

1 UNIT 3 Unit 3 began the month of December at a nominal 100% power.

On December 1,1993 at 22:00 hours the unit was shutdown. This was due to RHR MO-2-10-25A being inoperable.

On December 15,1993 at 21:00 hours the Unit 3 outage ended when the main generator was synchronized to the grid.

.i On December 171993 at 21:00 hours Unit 3 reached 100% power.

j On December 29,1993 at 21:00 hours power was reduced due to a recirc pump runback on 'A' pump. The unit was returned to 100% nominal power at 00:00 hours on December 30,1993.

Unit 3 ended the month at 100% nominal power.

The following maintenance outages occured on Unit 3:

  • Turbine Building Ventilation Heating Coils
  • Reactor Building Closed Cooling Water

~,.

t Docket No. 50-277 J

Attachment to

- Monthly Operating Report for December 1993 l

UNIT 2 REFUEUNG INFORMATION 1.

Name of facility:

Peach 30ttom Unit 2 2.

Scheduled date for next refueling shutdown:

Reload 10 scheduled for September 10,1994.

E i

3.

Scheduled date for restart following refueling:

Restart following refueling forecast for December 8,1994.

4.

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

l No.

i if answer is yes, what, in general, will these be?

5.

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

N/A i

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:

I 1

N/A i

I 7.

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

(a) Core - 764 Fuel Assemblies (b) Fuel Pool - 2164 Fuel Assemblies,58 Fuel Rods 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:

The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies,

Docket No. 50-277 Attachment to Monthly Operating Report for December 1993 Page 2 UNIT 2 REFQELING INFORMATipe (Continued) 9.

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

P September 2003 without full core offload capability.

September 1997 with full core offload capability.

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Docket 12o. 50-278 Attachment to.

i Monthly Operating i

Report for December 1993 UNIT 3 REFUELING INFORMATION l

1.

Name of facility:

Peach Bottom Unit 3 i

i 2.

Scheduled date for next refueling shutdown:

t Reload 10 scheduled for September 11,1995 j

3.

Scheduled date for restart following refueling Restart following refueling scheduled for November 13,1995 4.

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

No if answer is yes, what, in general, will these be?

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

i N/A 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or i

supplier, unreviewed design or performance analysis methods, significant changes in fuel design, l

new operating procedures:

N/A 7.

The nurnber of fuel assemblies (a) in the ' core and (b) in the spent fuel storage pool:

(a)

Core - 764 Fuel AssemNies (b)

Fuel Pool - 2201 Fuel Assemblies,6 Fuel Rods I

8.

The present licensed spent fuel pool storage capacity and the size of any increase.in licensed '

r storage capacity that has been requested or is planned, in number at fuel assemblies:

j The spent fuel pool storage capacity has been reticensed for 3819 fuel assemblies.

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l Docket No. 50-278 Attachment to Monthly Operating i

Report for December 1993 Page 2 l

F UNIT 3 REFUELING INFORMATION (Continued) i 9.

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

September 2004 without full core offload capability.

September 1998 with full core offload capability.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277 t

UNIT PEACH BOTTOM UNIT 2 t

DATE JkNhkRh kh,hh9k

' ^""

8.-

i COMPANY PECO ENERGY COMPANY W. J. JEFFREY r

PERFORMANCE & RELIABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027 I

MONTH DECEMBER 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DA!LY POWER LEVEL (MWE-NET )

(MWE-NET)

?

1 1D60 17 1068 2

1064 18 749 i

3 1064 19 991 4

' D60 20 1066 5

1060 21 1070 t

6 1061 22 1070 7

1061 23 1053 8

1061 24 1069 9

1066 25 1069 10 1061 26 1065 l

11 1065 27 1069 l

12 1065 28 1065 13 1064 29 1065

{

14 1065 30 1056 15 1063 31 1044 16 1071 e

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AVERACE DAILY UNIT POWER LEVEL

)

DOCKET No. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE JANUARY 11,1994 COMPANY PECO ENERGY COMPANY V. J. JEFFREY PERFORMANCE & RELIABILITY SITE ENGINEER 161G PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027 I

MONTH DECEMBER 1993 i

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DAY AVFRAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL f

(MWE* NET)

(MWE NET) i t

1 1036 17 811 I

2 80 18 1041 3

0 19 1058 4

0 20 1070

'5 5

0 21 1074 6

0 22 1066 i

7 0

23 1057 8

0 24 1066 9

0 25 1070 i

10 0

26 1061 i

11 7

27 1069 12 0

28 1065 1

1 13 0

29 1057 i

14 0

30 1065 a

15 6

31 1061 1

16 287 i

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OPERATING DATA REPORT l

DOCKET NO. 50 - 277 DATE JANUARY 11,1994 COMPLETED BY PECO ENERGY COMPANY'.........

W. J. JEFFREY PERFORMANCE & RELIABILITY l

SITE ENGINEERING i

PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT, 4027

- i OPERATING STATUS

1. UN!T NAME: PEACH BOTTOM UNIT 2 NOTES:
2. REPORTING PERIOD: DECEMBER, 1993

_ j

3. LICENSED THERMAL POWER (MWT):

3293 l

4. NAMEPLATE RATING (GROSS MWE):

1152

5. DESIGN ELECTRICAL RATING (NET MWE):

1065

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

1055 l

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY INET MWE):

?

10. REASONS FOR RESTRICTIONS, IF ANY:

t THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PER100 744 8,760 170,880

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12. NUMBER OF HOURS REACTOR WAS CRITICAL hk b h,hhbb bb,h2.
13. REACTOR RESERVE SHUTDOWN HOURS bb bb bb
14. HOURS GENERATOR ON-LINE hIkb hShk$b 5bh,hhb$h
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GRO$$ THERMAL ENERGY GENERATED (MWH) 2,418,406 24,119,749 3D4,489,493
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 806,200 7,979,100 100,151,490 i
18. NET ELECTRICAL ENERGY GENERATED (MWH) hb5kbh hTbkbk3 95,99bbbh PAGE 1 0F 2-k h

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t OPERATING DATA REPORT (CONTINUED).

DOCKET _ NO. 50 - 277 i

l DATE JANUARY 11,1994 6

THIS MONTH YR TO-DATE CUMULATIVE-

19. UNIT SERVICE FACTOR 100.0 86.4 59.8 i
20. UNIT AVAILABILITY FACTOR 100.0 86.4 59.8
21. UNIT CAPACITY FACTOR (USING MDC NET) 99.6 83.4 53.2
22. UNIT CAPACITY FACTOR (USING DER NET) 98.7 82.6 52.7 j
23. UNIT FORCED DUTAGE RATE b$b 5$5

"" II5$9

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

'k

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED I

JNITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 COMMERCIAL OPERATION 07/05/74

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OPERATING DATA REPORT DOCKET No. 50 - 278 DATE JANUARY 11,1994 COMPLETED BY PECO ENERGY COMPANY 7

W. J. JEFFREY

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PERFORKANCE & RELIABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027 OPERATING STA1US

1. UNIT NAME: PEACH BOTTOM UNIT 3 NOTES:

I

2. REPORTING PERIOD: DE CEMBER, 1993
3. LICENSED THERMAL POWER (MWT):

3293

4. NAMEPLATE RATING (GROSS MWE):

1152 I

5. DESIGN ELECTRICAL RATING (NET MWE):

1065 1

6. MAXIMON DEPENDABLE CAPACITY (GROSS MWE): 1098

~

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

1035

8. If CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

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11. HOURS IN REPORTING PER100 744 B,760 166,776 1

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12. NUMBER OF HOURS REACTOR WAS CRITICAL difb 6633b

~~kb,bfi$E

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 i
14. HOURS GENERATOR ON-LINE 417.0 6,594.0 101,291.2 l
15. UNIT RESERVE SHU1DOWN HOURS hh bh hh
16. GRO$$ THERMAL ENERGY GENERATED (MWH) 1,303,896 20,192,267 298,773,477
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 423,000 6,550,000 97,990,132 7
18. NET ELEC1RICAL ENERGY GENERATED (MWH) 408,740 6,310,370 93,974,336 PAGE 1 0F 2 j

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OPERATING DATA REPORT (CONTINUED)

DOCKET NO. 50 + 278 DATE JANUARY 11,1994 I

r THIS MONTH YR-TO-DATE CUMULATIVE i

19. UNIT SERVICE FACTOR 56.0 75.3 60.7

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20. UNIT AVAILABILITY FACTOR 56.0 75.3

_60.7 t

21. UNIT CAPACITY FACTOR (USING MDC NE1) 53.1 69.6 54.4
22. UNIT CAPACITY FACTOR (UsihG DER kET) 51.6 67.6 52.9 1
23. UNIT FORCED DUTAGE RATE 44.0 6.8 12.3
24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATIDN OF EACH):
25. IF SHUTDOWN AT END OF REPCRT PER100, ESTIMATED DATE OF STARTUP: 11/14/95
26. 05:T5 IN TEST STATUS (PRIOR TO COMMERCIAL DPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 i

INITIAL ELECTRICITY 09/01/74

[

COMMERCIAL OPERATION 12/23/74 b

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i UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50 - 277 t

UNIT NAME PEACH BOTTOM UNIT 2

{

DATE JANUARY 11,1994 REPORT MONTH DE CEMBER, 1993 COMPLETED BY PECO ENERGY COMPANY i

W. J. JEFFREY PERFORMANCE & RELIABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT, 4027 i

METHOD OF l t!CENSEE jsYSTEMlCOMPONENTj CAUSE AND CORRECTIVE l

T1PE DURATION REASON SHUTTING DOWN!

EVENT j CODE l CODE l ACTION TO Wo.

DATE (1)

(HOURS)

(2)

REAC10R (3) l REPORT # l (4) l (5) l PREVENT RECURRENCE l

t 9

4 26 931210 S1 2.0 B

4 N/A j RC l CONROD CONTROL ROO STROKlNG. REACTOR NOT SHUTDOWN I

27 931219 F

41.0 B

4 N/A RC CONROD ROD PATTERN ADJUSTMENT AND REACTOR FEED PUMP' l

MAINTENANCE. REACTOR NOT SHUTDOWN I

I 28 931231 Sl 3.0 B

4 N/A HE VALVEX TURBINE STOP VALVE TESTING.

REACTOR NOT SHUTDOWN I

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(1)

(2)

(3)

(4)

F* FORCED REASON METHOD EXHIBIT G. INSTRUCT 10NS S - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA i

B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE i

C - REFUELING-3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 OTHER (EXPLAIN)

FILE (NUREG-0161)

E OPERATOR TRAINING + LICENSE EXAMINATION F = ADMINISTRATIVE (5)

G - OPERATIONAL ERROR (EKPLAIN)

H OTHER(EXPLAIN)

EXHIBIT 1.SAME SOURCE i

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L UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE JANUARY 11,1994 REPORT MONTH DECEMBER,1993 COMPLETED BY PECO ENERGY COMPANY V. J. JEFFREY PERFORMANCE & RELIABILITY i

I SITE ENGINEERING PEACH BOTTOM ATOMIC POWEk STATION I

TELEPHONE (717) 456-7014 EXT. 4027 l

l METHOD OF l LICENSEE - SYSTEM COMPONENT' CAUSE AND CDRRECTIVE TYPE lDURATIONjREA50Nf'SHUTTINGDOWNj EVENT CODE CODE ACTION TO No.

DATE (1)l(HOURS)j (2) l REACTOR (3) l REPORT #

(4)

(5)

PREVENT RECURRENCE I

l 25 931201 F

335.0 l A

1 N/A SF lVALVEX LPCI MOTOR OPERATED VALVE Mo-25A INOPERABLE i

l 26 931229 F

3.0 j A

4 N/A CB PUMPXX "A" RECIRC PUMP RUNBACK. REACTOR NOT SHUTDOWN e

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l 338.0 l l

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(1)

(2)

(3)

(4)

)

F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS 5 SCHEDULED A - EQUIPMENT FA! LURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA I

B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SNEETS FOR LICENSEE

]

C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

J D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (NUREG-0161)

E

  • OPERATOR 1 RAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)

G - OPERATIONAL ERROR (EXPLAIN)

~i H-OTHER(EXPLAIN)

EXHIBIT I - SAME SOURCE l

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