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                                              . . . _ _ . . . _ _ ____ ___- ..____.___ ____. ..                                      __..o.._-           , . - - .            .
._._._ _..., ~.....
l CPERATING DATA REPORT DOCKET No. 50 - 277 D&TE BARCE 10 , 1983
__..o.._-
* CORPLETED BT PHILADELPHIA ELECTRIC COMPANT N.B.1LDE3 ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPROBE (215) 841-5022 OPERATING STATUS I
l CPERATING DATA REPORT DOCKET No. 50 - 277 D&TE BARCE 10, 1983 CORPLETED BT PHILADELPHIA ELECTRIC COMPANT N.B.1LDE3 ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPROBE (215) 841-5022 OPERATING STATUS
: 1. UNIT N&BE: PEACH BOTT05 UNIT 2                                         l NOTES: UNIT 2 EIPERIENCED TWO                                               g
: 1. UNIT N&BE: PEACH BOTT05 UNIT 2 l NOTES: UNIT 2 EIPERIENCED TWO I
                                      ..__...___...__........ ____                            g SCHEDULED LOAD REDUCTIONS.                                      l
g g
: 2. REPORTING PERIOD: FEBRUARI, 1983                                       l                                                                             g
: 2. REPORTING PERIOD: FEBRUARI, 1983 l
__________________ _____._                      g 3293                                                                                      I
SCHEDULED LOAD REDUCTIONS.
: 3. LICENSED THERMAL POWER (BUT) :                                         I                                                                             g
l g
___.___________.                g l
g I
: 4. NAMEPLATE R& TING (GROSS BWE) : _______..______1152                  l g
: 3. LICENSED THERMAL POWER (BUT) :
g 1065                                                                                      I
3293 I
: 5. LESIGN ELECTRICAL RATING (NET BWE) :                                 i                                                                             g
g g
                                                                        ....___..            g l
l
: 6. RAIIMU5 DEPENDABLE CAPACITY (GROSS EWE): 1098                         l                                                                             g
: 4. NAMEPLATE R& TING (GROSS BWE) :
                                                                                  ....        g 1051                                                                                        l
1152 l
: 7. M&IIMUM DEPENDABLE CAPACITY (WET BWE):                                 l B. IF CHANGES OCCUR IN CAPACITT RATINGS (ITEMS NU5BER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
g g
I
: 5. LESIGN ELECTRICAL RATING (NET BWE) :
1065 i
g g
l
: 6. RAIIMU5 DEPENDABLE CAPACITY (GROSS EWE): 1098 l
g g
l
: 7. M&IIMUM DEPENDABLE CAPACITY (WET BWE):
1051 l_ _ _ _. _. _ _ _ _.... _ _ _............. _ _.. _ _ _ _. _
B. IF CHANGES OCCUR IN CAPACITT RATINGS (ITEMS NU5BER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
: 9. POWER LEYEL TO WHICH RESTRICTED, IF ANT (WET MWE):
: 9. POWER LEYEL TO WHICH RESTRICTED, IF ANT (WET MWE):
: 10. REASONS FOR RESTRICTIONS, IF ANY:
: 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH             TR-TO-DATE                             COMULATITE 672                               1,416                         75,864
THIS MONTH TR-TO-DATE COMULATITE 672 1,416 75,864
: 11. HOURS IN REPORTING PEEIOD 672.0                       1,408.7                           56,498.4
: 11. HOURS IN REPORTING PEEIOD 672.0 1,408.7 56,498.4
: 12. NUBBER OF HOURS REnCTOR WAS CRITICAL 0.0                                   0.0                           0.0
: 12. NUBBER OF HOURS REnCTOR WAS CRITICAL 0.0 0.0 0.0
  ..                13. REACTOR RESERTE SHUTDOWN HOURS 672.0                         1,395.8                         54,944.7
: 13. REACTOR RESERTE SHUTDOWN HOURS 672.0 1,395.8 54,944.7
: 14. HOURS GENERATOR ON-LINE                                         ..... . ..              ._-                  ---.__            __.....__...
: 14. HOURS GENERATOR ON-LINE 0.0 0.0 0.0
0.0                                 0.0                           0.0
: 15. UNIT BESERVE SHUTDOWN BOURS
: 15. UNIT BESERVE SHUTDOWN BOURS 2,180,078                 4,511,808                         161,020,780
: 16. GROSS THERB AL ENERGY GENERATED (55H) 2,180,078 4,511,808 161,020,780
: 16. GROSS THERB AL ENERGY GENERATED (55H)                           ...______...            ______.___..                            .___.__. __
: 17. GROSS ELECTRICAL ENERGY GENERATED (R55) 724,910 1,497,590 53,018,100
724,910               1,497,590                           53,018,100           '
_.-- _==._
: 17. GROSS ELECTRICAL ENERGY GENERATED (R55)                        _.-- _ ==._             _____.____ _                          ______.___._
: 18. NET ELECTRICAL ENERGY GENER ATED (BWB) 699,328 1,443,138 50,828,287 100.0 98.6 72.4
699,328                 1,443,138                           50,828,287
: 19. UNIT SERVICE FACTOR 100.0 98.6 72.4
: 18. NET ELECTRICAL ENERGY GENER ATED (BWB) 100.0                                 98.6                         72.4
: 20. UNIT ATAILABILITY FACTOR 99.0 97.0 63.7 21, UNIT CAPACITY FACTOR (USING RDC RET)
: 19. UNIT SERVICE FACTOR 100.0                                 98.6                         72.4
: 22. UNIT CAP & CITY FACTOR (USING DER NET) 97.7-..
: 20. UNIT ATAILABILITY FACTOR                                       ..... .. __              ...___....._                            ..__. .. __
- - - 9 5.7 62.9 0.0 1.4 7.5
99.0                                 97.0                         63.7 21, UNIT CAPACITY FACTOR (USING RDC RET)                             _.._____..              ...__...____                            -.__._.__.__
: 23. UNIT FORCED OUTAGE B ATE
                                                                                          .         97.7-..         - - - 9 5.7                       .              62.9
=...___--
: 22. UNIT CAP & CITY FACTOR (USING DER NET) 0.0                                 1.4                         7.5
- =.
                                                                                                                                                                =...___--
: 23. UNIT FORCED OUTAGE B ATE                                         .....-......            - = .                   - __
: 24. SHUTDOWNS SCHEDULED OYER NEIT 6 MONT85 (TT PE, D ATE,1JD DUR ATION OF EACH) :
: 24. SHUTDOWNS SCHEDULED OYER NEIT 6 MONT85 (TT PE, D ATE,1JD DUR ATION OF EACH) :
AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
: 25. IF SHUTDOWN FORECAST                        ACHIEVED
: 25. IF SHUTDOWN
;                    26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPER ATION) :
: 26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPER ATION) :
INITIAL CRITICALITY                                             _____.___                        ___.....
FORECAST ACHIEVED INITIAL CRITICALITY IAL ELECTRICITY 8303160338 830311
IAL ELECTRICITY                                         -=           - -                --------
-=
8303160338 830311 PEwt ADOCK 05000277         PDR
PEwt ADOCK 05000277
:ERCIAL OPERATION                                         _____ __.                        ..______
:ERCIAL OPERATION PDR R
R


o
s.
  . . . . . . - . . . . .    . . . ,                _ - .      . _ -                                                          s.    .        .
o OPER ATING DATA REPORT DOCKET No. 50 - 178 DATE BARCH 10, 1983 COBPLETED BY PHILADELPHIA ELECTRIC COMPANY W.R.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NGCLEAR TELEPHONE (215) 841-5022 OPERATING STATUS
OPER ATING DATA REPORT DOCKET No. 50 - 178 DATE BARCH 10 , 1983 COBPLETED BY PHILADELPHIA ELECTRIC COMPANY W.R.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NGCLEAR TELEPHONE (215) 841-5022 OPERATING STATUS i
: 1. UNIT WhME: PEACH NOTTOM UNIT 3 l NOTES: UNIT 3 EIPERIENCED ONE i
: 1. UNIT WhME: PEACH NOTTOM UNIT 3 l NOTES: UNIT 3 EIPERIENCED ONE                                           i
i g
_..._. _______...___..___._.______              g SCHEDULED SHUTDONN.                                        I
: 2. REPORTING PERIOD: FEBRUARY, 1903 l
: 2. REPORTING PERIOD: FEBRUARY, 1903                                 l                                                                         l
SCHEDULED SHUTDONN.
________.____....___.__..__            g l
I l
3293       l                                                                         i
g l
: 3. LICENSED THERM AL POWER (BWT) : ..______________                g l .
3293 l
1152       l
: 3. LICENSED THERM AL POWER (BWT) :
* g
i g
: 4. NABEPLATE BATING (GROSS BWEs: .....__._______                    g l
l 1152 l
1065        l
: 4. NABEPLATE BATING (GROSS BWEs:
: 5. DESIGN ELECTRICAL RATING (NET BWE): ___. ___                      g g
g g
l l
l
: 6. BAIIMUM DEPENDABLE CAPACITY (GROSS sWE):_ 1098       _ _ _      g g
: 5. DESIGN ELECTRICAL RATING (NET BWE):
l 1035        l
1065 l
g g
l
: 6. BAIIMUM DEPENDABLE CAPACITY (GROSS sWE): 1098 l
g g
l
: 7. BAII505 DEPENDABLE CAPACITY (NET ENE):
: 7. BAII505 DEPENDABLE CAPACITY (NET ENE):
1035 l
: 8. IF CH ANGES OCCUR IN CAPACITY RATINGS (ITERS NUMBER 3 THROUGH 7) SINCE LAST REPORT, G
: 8. IF CH ANGES OCCUR IN CAPACITY RATINGS (ITERS NUMBER 3 THROUGH 7) SINCE LAST REPORT, G
: 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 50 NTH             YR-TO-DATE                     CUBULATIVE 672                     1,416                       71,760
THIS 50 NTH YR-TO-DATE CUBULATIVE 672 1,416 71,760
: 11. BOURS IN REPORTING PERIOD 316.5                 1,039.3                       54,969.0
: 11. BOURS IN REPORTING PERIOD 316.5 1,039.3 54,969.0
: 12. NUMBER OF BOURS REACTOR WAS CRITICAL                                               ..___ __.___                    __.______. _
: 12. NUMBER OF BOURS REACTOR WAS CRITICAL 0.0 0.0 0.0
0.0                         0.0                         0.0
: 13. REACTOR RESERVE SHUTDOWN HOURS
: 13. REACTOR RESERVE SHUTDOWN HOURS                           . . . . = _ - -
.... = _ - -
309.8                 1,026.3                     53,62'.1
309.8 1,026.3 53,62'.1
: 14. ROU25 GENER ATOR ON-LINE 0.0                       0.0                           0.0
: 14. ROU25 GENER ATOR ON-LINE 0.0 0.0 0.0
: 15. UNIT BESERVE SHUTDOWN BOURS 793,824                 2,742,355                   155,957,983
: 15. UNIT BESERVE SHUTDOWN BOURS
: 16. GROSS THERMAL ENERGY GENERATED (MWH)                     ..______....              ..._____.___                  ____.
: 16. GROSS THERMAL ENERGY GENERATED (MWH) 793,824 2,742,355 155,957,983
257,670                   894,560                   51,136,090
: 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 257,670 894,560 51,136,090
: 17. GROSS ELECTRICAL ENERGY GENERATED (MWH)                                                     = - = - - -            . _____.....
= - = - - -
241,283                   848,889                   49,091,681
: 18. NET ELECTRICAL ENERGY GENERATED (MWH) 241,283 848,889 49,091,681 46.1 72.5 74.7
: 18. NET ELECTRICAL ENERGY GENERATED (MWH)                                                                              __
: 19. UNIT SERVICE F19?OR
46.1                       72.5                         74.7
=
: 19. UNIT SERVICE F19?OR                                                                                                 __..-                  =
46.1 72.5 74.7 i
46.1                       72.5                         74.7 i                 20. UNIT AT&ILABILITY FACTOR                                       , - --_____          .._.._ --_--
: 20. UNIT AT&ILABILITY FACTOR 34.7 57.9 66.1
34.7                       57.9                         66.1
: 21. UNIT CAPACITY FACTOR (U$ING HDC NET)
: 21. UNIT CAPACITY FACTOR (U$ING HDC NET)                       _______...__              .....
: 22. UNIT CAPACITY PACTOR (USING DER NET) -
                                                                                      -    - 33.7                       56.3                         64.2
- 33.7 56.3 64.2
: 22. UNIT CAPACITY PACTOR (USING DER NET) -                                                  = =-- =-__                 ___..______.
= =-- =-__
0.0                       2.6                             7.3
0.0 2.6 7.3
: 23. UNIT FORCED OUTAGE RATE                                                     --
: 23. UNIT FORCED OUTAGE RATE
__= =--__
__= =--__
: 24. SHUTDOWNS SCHEDULED OVER NEIT 6 BONTHS (TT PE, D ATE, AND DURATION OF ZACH):
SHUTDOWNS SCHEDULED OVER NEIT 6 BONTHS (TT PE, D ATE, AND DURATION OF ZACH):
SCHEDULED SHUTDOWN FOR REFUELING AND MAINTEN ANCE, STARTED 2/13/83, FOR ELEWEN WEEK OUTAGE.
24.
f 5/2/83
SCHEDULED SHUTDOWN FOR REFUELING AND MAINTEN ANCE, STARTED f
2/13/83, FOR ELEWEN WEEK OUTAGE.
: 25. IF SHUTDOWN AT EMD OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
: 25. IF SHUTDOWN AT EMD OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
FORECAST                  ACHIEVED
5/2/83
: 26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATION) :
: 26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATION) :
INITIAL CRITICALITY                                   ________.                       --..
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
INITIAL ELECTRICITY                                    .________                ________
 
COMMERCIAL OPERATION                                                              ____..__
l l
d
~
t
.1 UNIT SHUTDONMS AND PONER REDUCTIONS DOCKET Wo. 50 - 277 l.
UNIT MARE PEACH BOTTON UNIT 2 f.
_=
DATE BARCH 10, 1983 REPORT MONTH FEBRUARY, 1983 C05PLETED BY PMILADELPHIA ELECTRIC COMPANY en N.R.ALDEN E NGIN EER-IN-CH ARGE NUCLEAR SECTION
]
GENERATION DIVISION-NUCLEA R TELEPHONE (215) 841-5022
=
--==
l!
_=-
_==
j l
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l l NETHOD OF l LICENSEE lSYSTE5l COMPONENT l CAUSE AND CORRECTIVE l
1 lTYPElDURATIONlREASONISHUTTING TONNl EVENT l CODE I CODE I ACTION To NO.l DATE l (1) l (HOU RS) l (2) l REACTOR g3) l REPORT 8 l (4) l (5) l PREVENT RECURRENCE j


==
==
-----=
.. -- =_
1 I
I i
1 I
I I
I 2l 830201 l S l 00.0 I
B i 4
l 54 l BC l ZZZZZZ l LO&D REDUCTION FOR CONTROL ROD PATTERN EI l
l l
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l l ADJU STMENT.
1 I
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1 1
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1 3 1 830205 l S I 00.0 l
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l Na l HF l HTEICE l LOAD REDUCTION FOR N&TERSOI REPAIR AND 1
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          ~
l a - REACTOR FEED PURP TUR8INE LUBE.
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.1                                                      UNIT SHUTDONMS AND PONER REDUCTIONS                      DOCKET Wo. 50 - 277 l.
1 1
UNIT MARE PEACH BOTTON UNIT 2
1 1
: f.                                                                                                                                                                                        _=
1 1
DATE BARCH 10 , 1983
1 I
  '      en                                                REPORT MONTH FEBRUARY, 1983                      C05PLETED BY PMILADELPHIA ELECTRIC COMPANY N.R.ALDEN
i i
  '      #'                                                                                                                    E NGIN EER-IN-CH ARGE NUCLEAR SECTION
i 1 -
] ,
1 I
GENERATION DIVISION-NUCLEA R
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  !                                                                                                                TELEPHONE (215) 841-5022                                                                  --
1 I
                                                                                                                                =    --==                        _
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(1)
_==              __ _                --------          -            __                                      -
(2)
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(3)
l        l    l            l          l NETHOD OF l LICENSEE lSYSTE5l COMPONENT l CAUSE AND CORRECTIVE l                  1         lTYPElDURATIONlREASONISHUTTING TONNl              EVENT    l CODE I      CODE I        ACTION To j            NO.l    DATE l (1) l (HOU RS) l          (2) l REACTOR g3) l REPORT 8 l      (4) l      (5)  l PREVENT RECURRENCE
(4)
          ,,  ==
F - FORCED REASON METHOD EINIBIT G - INSTRUCTIONS S - SCHEDULED A - EQUIPRENT FAILUBE (EIPL AIN) 1 - MANUAL FOR PREPAR& TION OF DATA B - MAINTENANCE OR TEST 2 - SANUAL SCRAM.
                                                                                                                          ==              -----=                              .. -- =_                        .------
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCR&M.
1         I      I            i          1             I            I        I          I 2l 830201 l S l          00.0    I      B i        4      l    54    l BC l ZZZZZZ l LO&D REDUCTION FOR CONTROL ROD PATTERN EI        l        l      l            l          l              l          l          l          l ADJU STMENT.
EVENT BEPORT (LER)
1         I      I            1         1              1          1          1         1 3 1 830205 l S I         00.0    l      H g        4        l    Na    l HF l HTEICE l LOAD REDUCTION FOR N&TERSOI REPAIR AND t 4#        1        1      l            !          l              1          l        l          l a - REACTOR FEED PURP TUR8INE LUBE.
D - REGULATORY RESTRICTION 4 - OTHER (EIPL&IN)
1        I      i -----
FILE (NU R EG-0161)
1        1              1          1          1          1 i        i     1 -           1         I               I           i         1         I y
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTR ATIVE (5)
Y
G - OPERATIONAL ERROR (EIPL&IN)
          %#          (1)                           (2)                                                 (3)                             (4)
H - OTHER (EXPLAIN)
F - FORCED           REASON                                                 METHOD                           EINIBIT G - INSTRUCTIONS
EIMIBIT I - SANE SOURCE 4
* S - SCHEDULED         A - EQUIPRENT FAILUBE (EIPL AIN)                       1 - MANUAL                       FOR PREPAR& TION OF DATA B - MAINTENANCE OR TEST                                 2 - SANUAL SCRAM.                 ENTRY SHEETS FOR LICENSEE C - REFUELING                                           3 - AUTOMATIC SCR&M.             EVENT BEPORT (LER)
b 0
* D - REGULATORY RESTRICTION                             4 - OTHER (EIPL&IN)                 FILE (NU R EG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTR ATIVE                                                                                 (5)
            --                        G - OPERATIONAL ERROR (EIPL&IN)
H - OTHER (EXPLAIN)                                                                     EIMIBIT I - SANE SOURCE 4       b 0
O G
O G
d i -
d i
8
8


DOCKET NO. 50 - 278 UNIT SHUTDONNS AND POWER REDUCTIONS                                     .
DOCKET NO. 50 - 278 UNIT SHUTDONNS AND POWER REDUCTIONS UNIT NAME PEACH BOTTOR UNIT 3 DATE 5 ARCH 10, 1983 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY REPORT MONTH FEBRUARY, 1983 W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022
UNIT NAME PEACH BOTTOR UNIT 3         . ...
---=-- -
DATE 5 ARCH 10 , 1983
l l
    ''                                                    REPORT MONTH FEBRUARY, 1983                     COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR
l l
      '                                                                                                      TELEPHONE (215) 841-5022
l NETE3D OF l LICENSEE lSYSTEHlCORPOWENTl CAUSE AND CORRECTIVE EVENT l CODE l CODE {
                                                                          ---=-- -
ACTION TO l
l         l       l             l         l NETE3D OF l LICENSEE   lSYSTEHlCORPOWENTl CODE {        CAUSETO ACTION    AND CORRECTIVE EVENT   l CODE l l         l TYPE l DURATION lBEASONl SHUTTING DONNI                         (4) l    (5)  l PREVENT RECURRENCE
l TYPE l DURATION lBEASONl SHUTTING DONNI NO.I DATE i (1)l (HOURS) l (2) l REACTOR (3) l BEPORT 8 l (4) l (5) l PREVENT RECURRENCE I
    ,,  NO.I       DATE i (1)l (HOURS) l           (2) l REACTOR (3) l BEPORT 8 l I             I       f          f I       I       I             I           I C l         1             NA   I RC l FUELII l SHUTDONE FOR REFUELING OUTAGE.
I I
3 1 830213 i S I 362.2 l                       I 1
I I
I            I        I          I 1        l      1 ----- 1                                           l        l          l I       l       1 362.2 I                 l           t
I I
      ;)
f f
3 1 830213 i S I 362.2 l C l 1
1 NA I RC l FUELII l SHUTDONE FOR REFUELING OUTAGE.
1 l
1 ----- 1 I
I I
I I
I l
1 362.2 I l
t l
l l
;)
c W
c W
(3)                             (4)
(3)
(1)                           (2)
(4)
METHOD                        EIRIBIT C - INSTRUCTIONS F - FORCED              REASON                                                  1 - MANUAL                   FOR PREP AR ATION OF DATA S - SCHEDULED          A - EQUIPMENT FAILURE (EIPLAIN)                          2 - 5ANUAL SCR&B.             ENTRY SHEETS FOR LICENSEE
(1)
      %d                          B - HAINTENANCE OR TEST                                 3 - AUTOMATIC SCRAM.         EVENT REPORT (LER)
(2)
C - REFUELING                                           4 - OTHER (EIPLAIN)               FILE (NU REG-0161)
EIRIBIT C - INSTRUCTIONS METHOD S - SCHEDULED A - EQUIPMENT FAILURE (EIPLAIN) 1 - MANUAL FOR PREP AR ATION OF DATA F - FORCED REASON 2 - 5ANUAL SCR&B.
D - REGULATORY RESTRICTION                              ~
ENTRY SHEETS FOR LICENSEE B - HAINTENANCE OR TEST 3 - AUTOMATIC SCRAM.
      '                          E - OPERATOR TRAINING + LICENSE EIABINATION                                                       (5)
EVENT REPORT (LER)
F - ADMINISTRATIVE G - OPERATIONAL ERROR (EIPLAIN)                                                       BIMIBIT I - SABE SOUACE H - OTHER (EIPLAIN) e
%d C - REFUELING D - REGULATORY RESTRICTION
~
(EIPLAIN)
FILE (NU REG-0161) 4 - OTHER E - OPERATOR TRAINING + LICENSE EIABINATION (5)
F - ADMINISTRATIVE G - OPERATIONAL ERROR (EIPLAIN)
BIMIBIT I - SABE SOUACE H - OTHER (EIPLAIN) e


AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE MARCH 10 , 1983 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH     FEBRUARY 1983 DAY   AVERAGE DAILY POWER LEVEL             DAY       AVERAGE DAILY POWER LEVEL (MWE-NET)                                         (MWE-NET) 1                   827                     17                           1057 2                   1047                     18                           1054 3                   1049                     19                           1054 4                   1051                     20                           1052 5                   904                     21                           1050 6              -
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE MARCH 10, 1983 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH FEBRUARY 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
1054                     22                           1049 7                   1060                     23                           1052
(MWE-NET) 1 827 17 1057 2
                                                                    ~
1047 18 1054 3
8                   1061                     24                           1050 9                   1060                     25                           1050 10                   1059                     26                           1052 l
1049 19 1054 4
i            11                   1059                     27                           1051 12                   1057                     28                           1050 l
1051 20 1052 5
l           13                   1056 1
904 21 1050 1054 22 1049 6
14                   1057 15                   1059 l             16                   1059 1
7 1060 23 1052
\
~
8 1061 24 1050 9
1060 25 1050 l
10 1059 26 1052 i
11 1059 27 1051 12 1057 28 1050 l
l 13 1056 1
14 1057 15 1059 l
16 1059 1
\\
l
l


i ATERAGE DAILY UNIT POWER LEVEL                                                                     i
i ATERAGE DAILY UNIT POWER LEVEL i
                                                                                                                                        )
DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE MARCH 10, 1983 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH FEBRUARY 1983 DAY AYERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE MARCH 10 , 1983 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH   FEBRUARY 1983 DAY     AYERAGE DAILY POWER LEVEL                     DAY         AVERAGE DAILY POWER LEVEL (MWE-NET)                                                   (M WE-NET) 1                           821                       17                                 0 2                           815                       18                                 0 3                           808                       19                                 0 4                           805                       20                                 0 5                           802                       21                                 0                             ,
(M WE-NET) 1 821 17 0
6                           797                       22                                 0
2 815 18 0
,,          7                           799                       23                                 0 8                           794                       24                                 0 9                           790                       25                                 0 10                           786                       26                                 0 11                           783                       27                                 0 12                           779                       28                                 0 13                           667 14                             0 15                             0 16                             0
3 808 19 0
4 805 20 0
5 802 21 0
6 797 22 0
7 799 23 0
8 794 24 0
9 790 25 0
10 786 26 0
11 783 27 0
12 779 28 0
13 667 14 0
15 0
16 0


      .                                                          Dockst No. 50-277 Attachm:nt to Monthly Operating Rsport For Month of February,1983 REPU P.I,I NG I:WO;01ATION
Dockst No. 50-277 Attachm:nt to Monthly Operating Rsport For Month of February,1983 REPU P.I,I NG I:WO;01ATION 1.
: 1. Name of facility:
Name of facility:
Peach Bottom Unit 2
Peach Bottom Unit 2 2.
: 2. Scheduled date for next refueling shutdowns, October 15, 1983                                                         ,
Scheduled date for next refueling shutdowns, October 15, 1983 3.
: 3. Scheduled date for restart following refuelings.
Scheduled date for restart following refuelings.
January -14,~ 1984
January -14,~ 1984 4.
: 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes If answer is yes, what, in general, will these be?
Yes If answer is yes, what, in general, will these be?
Technical specifications to accommodate reload fuel.
Technical specifications to accommodate reload fuel.
Modifications to reactor core operating limits are expected.
Modifications to reactor core operating limits are expected.
: 5. Scheduled date(s) for submitting proposed licensing action and supporting information:
5.
      .            September 10, 1983         '                  '
Scheduled date(s) for submitting proposed licensing action and supporting information:
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 j                   None expected                                                     ,
September 10, 1983 6..
  ,      7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a) Core - 764 Fuel Assemblies (b) Fuel Pool - 1170 Fuel Assemblies, 58 Fuel Rods
Important licensing considerations associated with refueling, e.g.,
: 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:
new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures j
l                   The spent fuel pool storage capacity has been relicensod
None expected 7.
;                  for 2816 fuel assemblies.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a)
: 9. The projected date of the last refueling that can be discherged to the spent fuel pool assuming the present licensed capacity.
Core - 764 Fuel Assemblies (b)
Fuel Pool - 1170 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:
l The spent fuel pool storage capacity has been relicensod for 2816 fuel assemblies.
9.
The projected date of the last refueling that can be discherged to the spent fuel pool assuming the present licensed capacity.
March, 1990 (September, 1985 with reserve for full core discharge i
March, 1990 (September, 1985 with reserve for full core discharge i
                                        -..                                          s t
s t


Docht No. 50-278 Attachm:nt to Monthly Operating Rsport For Month of February,1983 REPUELT!iG TNPORMATION
Docht No. 50-278 Attachm:nt to Monthly Operating Rsport For Month of February,1983 REPUELT!iG TNPORMATION 1.
: 1. Name of facility:
Name of facility:
Peach Bottom Unit 3
Peach Bottom Unit 3 2.
: 2. Scheduled date for next refueling sh.utdown:
Scheduled date for next refueling sh.utdown:
February     3, 1983
February 3, 1983 3.
: 3. Scheduled date for restart following refueling:
Scheduled date for restart following refueling:
May 2, 1983
May 2, 1983 4.
: 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes If answer is yes, what, in general, will these be?
Yes If answer is yes, what, in general, will these be?
Technical specifications to accommodate reload fuel.
Technical specifications to accommodate reload fuel.
Modifications to reactor core operating linits are expected,
Modifications to reactor core operating linits are
: 5. Scheduled date(s) for submitting proposed licensing action and supporting information:
: expected, 5.
Submitted December 30, 1982
Scheduled date(s) for submitting proposed licensing action and supporting information:
: 6. Important licensing considerations associated with refueling, e.g., new or differ,ent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, now operating procedures None expected
Submitted December 30, 1982 6.
: 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a) Core - 764 Fuel Assemblies (b) Fuel Pool - 928 Fuel Assemblies, 6 Fuel Rods
Important licensing considerations associated with refueling, e.g.,
: 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:
new or differ,ent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, now operating procedures None expected 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a)
Core - 764 Fuel Assemblies (b)
Fuel Pool - 928 Fuel Assemblies, 6 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 2816 fuel assemblies.
The spent fuel pool storage capacity has been relicensed for 2816 fuel assemblies.
: 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
September, 1990 (March, 1986 with reserve for fuell core discharge r
September, 1990 (March, 1986 with reserve for fuell core discharge r
                                                              . - - . . , - . . . , _ . . . , , , . , , , , . ,              -.-      ,-- _,~ , - . _ _ . ,
,-- _,~,


x ..     v
x..
[ 'l x .-.
v
5: .
[ 'l 5:
Peach Bottom Atomic Power Station Narrative Summary of Ooerating Experiences Februsry   1993 Unit 2:
x.-.
The unit began the month at 700 MWe, reduced in power to perform a control rod pattern adjustment. Full power was reached early on February 2. On February 5, reactor power was again reduced to 700 MWe in order to remove the"B" reactor feed pump turbine from service for coupling lubrication and to repair tube leaks in the C-2 circulating water box. The unit was returned to full power on February 5 and remained at full power throuch the end of the month. On February 20, the E-1 emergency diesel generator was removed from service for its annual inspection. The E-1 diesel
Peach Bottom Atomic Power Station Narrative Summary of Ooerating Experiences Februsry 1993 Unit 2:
                      ~
The unit began the month at 700 MWe, reduced in power to perform a control rod pattern adjustment.
generator was tested and returned to service on February 26.
Full power was reached early on February 2.
On February 5, reactor power was again reduced to 700 MWe in order to remove the"B" reactor feed pump turbine from service for coupling lubrication and to repair tube leaks in the C-2 circulating water box.
The unit was returned to full power on February 5 and remained at full power throuch the end of the month.
On February 20, the E-1 emergency diesel generator was removed from service for its annual inspection.
The E-1 diesel generator was tested and returned to service on February 26.
~
Unit 3:
Unit 3:
The unit began the month at RO% power in extended core fl ow onaration, with the 5th feedwater heaters removed from service, during end of cycle coastdown. On February 1, an Unusual Event was declared when, during testing of ECCS systems, both the "A" Core Spray and High Pressure Coolant Injection systems became inoperable. The "A" Core Spray system was returned to service within 46 minutes and the Unusual Event was terminated. Following testing, the High Pressure Coolant Injection system was returned to service early on February 2. On February 7, the "A" RHR loop was removed from service for repairs to an RHR valve. The "A" RHR loop was returned to service on February 8. On February 10, the HPCT system was again removed from service in order to modify the hydraulic and electronic controls which set the HPCI system "ouick start" acceleration ramp. The unit's fifth refueling outage began on February 13. By February 18 reactor vessel head removal was complete and fuel off-load was begun on February 25. At the end of the month, main turbine disassembly was in progress, unlatching of CRD blades was underway and the reactor recirculation system piping IHSI program had begun.}}
The unit began the month at RO% power in extended core fl ow onaration, with the 5th feedwater heaters removed from service, during end of cycle coastdown.
On February 1, an Unusual Event was declared when, during testing of ECCS systems, both the "A" Core Spray and High Pressure Coolant Injection systems became inoperable.
The "A" Core Spray system was returned to service within 46 minutes and the Unusual Event was terminated.
Following testing, the High Pressure Coolant Injection system was returned to service early on February 2.
On February 7, the "A" RHR loop was removed from service for repairs to an RHR valve.
The "A"
RHR loop was returned to service on February 8.
On February 10, the HPCT system was again removed from service in order to modify the hydraulic and electronic controls which set the HPCI system "ouick start" acceleration ramp.
The unit's fifth refueling outage began on February 13.
By February 18 reactor vessel head removal was complete and fuel off-load was begun on February 25.
At the end of the month, main turbine disassembly was in progress, unlatching of CRD blades was underway and the reactor recirculation system piping IHSI program had begun.}}

Latest revision as of 11:17, 16 December 2024

Monthly Operating Repts for Feb 1983
ML20069A892
Person / Time
Site: Peach Bottom  
Issue date: 03/10/1983
From: Alden W
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20069A884 List:
References
NUDOCS 8303160338
Download: ML20069A892 (9)


Text

_.

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

__..o.._-

l CPERATING DATA REPORT DOCKET No. 50 - 277 D&TE BARCE 10, 1983 CORPLETED BT PHILADELPHIA ELECTRIC COMPANT N.B.1LDE3 ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPROBE (215) 841-5022 OPERATING STATUS

1. UNIT N&BE: PEACH BOTT05 UNIT 2 l NOTES: UNIT 2 EIPERIENCED TWO I

g g

2. REPORTING PERIOD: FEBRUARI, 1983 l

SCHEDULED LOAD REDUCTIONS.

l g

g I

3. LICENSED THERMAL POWER (BUT) :

3293 I

g g

l

4. NAMEPLATE R& TING (GROSS BWE) :

1152 l

g g

I

5. LESIGN ELECTRICAL RATING (NET BWE) :

1065 i

g g

l

6. RAIIMU5 DEPENDABLE CAPACITY (GROSS EWE): 1098 l

g g

l

7. M&IIMUM DEPENDABLE CAPACITY (WET BWE):

1051 l_ _ _ _. _. _ _ _ _.... _ _ _............. _ _.. _ _ _ _. _

B. IF CHANGES OCCUR IN CAPACITT RATINGS (ITEMS NU5BER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

9. POWER LEYEL TO WHICH RESTRICTED, IF ANT (WET MWE):
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH TR-TO-DATE COMULATITE 672 1,416 75,864

11. HOURS IN REPORTING PEEIOD 672.0 1,408.7 56,498.4
12. NUBBER OF HOURS REnCTOR WAS CRITICAL 0.0 0.0 0.0
13. REACTOR RESERTE SHUTDOWN HOURS 672.0 1,395.8 54,944.7
14. HOURS GENERATOR ON-LINE 0.0 0.0 0.0
15. UNIT BESERVE SHUTDOWN BOURS
16. GROSS THERB AL ENERGY GENERATED (55H) 2,180,078 4,511,808 161,020,780
17. GROSS ELECTRICAL ENERGY GENERATED (R55) 724,910 1,497,590 53,018,100

_.-- _==._

18. NET ELECTRICAL ENERGY GENER ATED (BWB) 699,328 1,443,138 50,828,287 100.0 98.6 72.4
19. UNIT SERVICE FACTOR 100.0 98.6 72.4
20. UNIT ATAILABILITY FACTOR 99.0 97.0 63.7 21, UNIT CAPACITY FACTOR (USING RDC RET)
22. UNIT CAP & CITY FACTOR (USING DER NET) 97.7-..

- - - 9 5.7 62.9 0.0 1.4 7.5

23. UNIT FORCED OUTAGE B ATE

=...___--

- =.

24. SHUTDOWNS SCHEDULED OYER NEIT 6 MONT85 (TT PE, D ATE,1JD DUR ATION OF EACH) :

AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

25. IF SHUTDOWN
26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPER ATION) :

FORECAST ACHIEVED INITIAL CRITICALITY IAL ELECTRICITY 8303160338 830311

-=

PEwt ADOCK 05000277

ERCIAL OPERATION PDR R

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o OPER ATING DATA REPORT DOCKET No. 50 - 178 DATE BARCH 10, 1983 COBPLETED BY PHILADELPHIA ELECTRIC COMPANY W.R.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NGCLEAR TELEPHONE (215) 841-5022 OPERATING STATUS

1. UNIT WhME: PEACH NOTTOM UNIT 3 l NOTES: UNIT 3 EIPERIENCED ONE i

i g

2. REPORTING PERIOD: FEBRUARY, 1903 l

SCHEDULED SHUTDONN.

I l

g l

3293 l

3. LICENSED THERM AL POWER (BWT) :

i g

l 1152 l

4. NABEPLATE BATING (GROSS BWEs:

g g

l

5. DESIGN ELECTRICAL RATING (NET BWE):

1065 l

g g

l

6. BAIIMUM DEPENDABLE CAPACITY (GROSS sWE): 1098 l

g g

l

7. BAII505 DEPENDABLE CAPACITY (NET ENE):

1035 l

8. IF CH ANGES OCCUR IN CAPACITY RATINGS (ITERS NUMBER 3 THROUGH 7) SINCE LAST REPORT, G
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS 50 NTH YR-TO-DATE CUBULATIVE 672 1,416 71,760

11. BOURS IN REPORTING PERIOD 316.5 1,039.3 54,969.0
12. NUMBER OF BOURS REACTOR WAS CRITICAL 0.0 0.0 0.0
13. REACTOR RESERVE SHUTDOWN HOURS

.... = _ - -

309.8 1,026.3 53,62'.1

14. ROU25 GENER ATOR ON-LINE 0.0 0.0 0.0
15. UNIT BESERVE SHUTDOWN BOURS
16. GROSS THERMAL ENERGY GENERATED (MWH) 793,824 2,742,355 155,957,983
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 257,670 894,560 51,136,090

= - = - - -

18. NET ELECTRICAL ENERGY GENERATED (MWH) 241,283 848,889 49,091,681 46.1 72.5 74.7
19. UNIT SERVICE F19?OR

=

46.1 72.5 74.7 i

20. UNIT AT&ILABILITY FACTOR 34.7 57.9 66.1
21. UNIT CAPACITY FACTOR (U$ING HDC NET)
22. UNIT CAPACITY PACTOR (USING DER NET) -

- 33.7 56.3 64.2

= =-- =-__

0.0 2.6 7.3

23. UNIT FORCED OUTAGE RATE

__= =--__

SHUTDOWNS SCHEDULED OVER NEIT 6 BONTHS (TT PE, D ATE, AND DURATION OF ZACH):

24.

SCHEDULED SHUTDOWN FOR REFUELING AND MAINTEN ANCE, STARTED f

2/13/83, FOR ELEWEN WEEK OUTAGE.

25. IF SHUTDOWN AT EMD OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

5/2/83

26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATION) :

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

l l

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.1 UNIT SHUTDONMS AND PONER REDUCTIONS DOCKET Wo. 50 - 277 l.

UNIT MARE PEACH BOTTON UNIT 2 f.

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DATE BARCH 10, 1983 REPORT MONTH FEBRUARY, 1983 C05PLETED BY PMILADELPHIA ELECTRIC COMPANY en N.R.ALDEN E NGIN EER-IN-CH ARGE NUCLEAR SECTION

]

GENERATION DIVISION-NUCLEA R TELEPHONE (215) 841-5022

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l l NETHOD OF l LICENSEE lSYSTE5l COMPONENT l CAUSE AND CORRECTIVE l

1 lTYPElDURATIONlREASONISHUTTING TONNl EVENT l CODE I CODE I ACTION To NO.l DATE l (1) l (HOU RS) l (2) l REACTOR g3) l REPORT 8 l (4) l (5) l PREVENT RECURRENCE j

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F - FORCED REASON METHOD EINIBIT G - INSTRUCTIONS S - SCHEDULED A - EQUIPRENT FAILUBE (EIPL AIN) 1 - MANUAL FOR PREPAR& TION OF DATA B - MAINTENANCE OR TEST 2 - SANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCR&M.

EVENT BEPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EIPL&IN)

FILE (NU R EG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTR ATIVE (5)

G - OPERATIONAL ERROR (EIPL&IN)

H - OTHER (EXPLAIN)

EIMIBIT I - SANE SOURCE 4

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DOCKET NO. 50 - 278 UNIT SHUTDONNS AND POWER REDUCTIONS UNIT NAME PEACH BOTTOR UNIT 3 DATE 5 ARCH 10, 1983 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY REPORT MONTH FEBRUARY, 1983 W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022

---=-- -

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l NETE3D OF l LICENSEE lSYSTEHlCORPOWENTl CAUSE AND CORRECTIVE EVENT l CODE l CODE {

ACTION TO l

l TYPE l DURATION lBEASONl SHUTTING DONNI NO.I DATE i (1)l (HOURS) l (2) l REACTOR (3) l BEPORT 8 l (4) l (5) l PREVENT RECURRENCE I

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EIRIBIT C - INSTRUCTIONS METHOD S - SCHEDULED A - EQUIPMENT FAILURE (EIPLAIN) 1 - MANUAL FOR PREP AR ATION OF DATA F - FORCED REASON 2 - 5ANUAL SCR&B.

ENTRY SHEETS FOR LICENSEE B - HAINTENANCE OR TEST 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

%d C - REFUELING D - REGULATORY RESTRICTION

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(EIPLAIN)

FILE (NU REG-0161) 4 - OTHER E - OPERATOR TRAINING + LICENSE EIABINATION (5)

F - ADMINISTRATIVE G - OPERATIONAL ERROR (EIPLAIN)

BIMIBIT I - SABE SOUACE H - OTHER (EIPLAIN) e

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE MARCH 10, 1983 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH FEBRUARY 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 827 17 1057 2

1047 18 1054 3

1049 19 1054 4

1051 20 1052 5

904 21 1050 1054 22 1049 6

7 1060 23 1052

~

8 1061 24 1050 9

1060 25 1050 l

10 1059 26 1052 i

11 1059 27 1051 12 1057 28 1050 l

l 13 1056 1

14 1057 15 1059 l

16 1059 1

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l

i ATERAGE DAILY UNIT POWER LEVEL i

DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE MARCH 10, 1983 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH FEBRUARY 1983 DAY AYERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(M WE-NET) 1 821 17 0

2 815 18 0

3 808 19 0

4 805 20 0

5 802 21 0

6 797 22 0

7 799 23 0

8 794 24 0

9 790 25 0

10 786 26 0

11 783 27 0

12 779 28 0

13 667 14 0

15 0

16 0

Dockst No. 50-277 Attachm:nt to Monthly Operating Rsport For Month of February,1983 REPU P.I,I NG I:WO;01ATION 1.

Name of facility:

Peach Bottom Unit 2 2.

Scheduled date for next refueling shutdowns, October 15, 1983 3.

Scheduled date for restart following refuelings.

January -14,~ 1984 4.

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

Yes If answer is yes, what, in general, will these be?

Technical specifications to accommodate reload fuel.

Modifications to reactor core operating limits are expected.

5.

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

September 10, 1983 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 j

None expected 7.

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

Core - 764 Fuel Assemblies (b)

Fuel Pool - 1170 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:

l The spent fuel pool storage capacity has been relicensod for 2816 fuel assemblies.

9.

The projected date of the last refueling that can be discherged to the spent fuel pool assuming the present licensed capacity.

March, 1990 (September, 1985 with reserve for full core discharge i

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Docht No. 50-278 Attachm:nt to Monthly Operating Rsport For Month of February,1983 REPUELT!iG TNPORMATION 1.

Name of facility:

Peach Bottom Unit 3 2.

Scheduled date for next refueling sh.utdown:

February 3, 1983 3.

Scheduled date for restart following refueling:

May 2, 1983 4.

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

Yes If answer is yes, what, in general, will these be?

Technical specifications to accommodate reload fuel.

Modifications to reactor core operating linits are

expected, 5.

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

Submitted December 30, 1982 6.

Important licensing considerations associated with refueling, e.g.,

new or differ,ent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, now operating procedures None expected 7.

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

Core - 764 Fuel Assemblies (b)

Fuel Pool - 928 Fuel Assemblies, 6 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 2816 fuel assemblies.

9.

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

September, 1990 (March, 1986 with reserve for fuell core discharge r

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Peach Bottom Atomic Power Station Narrative Summary of Ooerating Experiences Februsry 1993 Unit 2:

The unit began the month at 700 MWe, reduced in power to perform a control rod pattern adjustment.

Full power was reached early on February 2.

On February 5, reactor power was again reduced to 700 MWe in order to remove the"B" reactor feed pump turbine from service for coupling lubrication and to repair tube leaks in the C-2 circulating water box.

The unit was returned to full power on February 5 and remained at full power throuch the end of the month.

On February 20, the E-1 emergency diesel generator was removed from service for its annual inspection.

The E-1 diesel generator was tested and returned to service on February 26.

~

Unit 3:

The unit began the month at RO% power in extended core fl ow onaration, with the 5th feedwater heaters removed from service, during end of cycle coastdown.

On February 1, an Unusual Event was declared when, during testing of ECCS systems, both the "A" Core Spray and High Pressure Coolant Injection systems became inoperable.

The "A" Core Spray system was returned to service within 46 minutes and the Unusual Event was terminated.

Following testing, the High Pressure Coolant Injection system was returned to service early on February 2.

On February 7, the "A" RHR loop was removed from service for repairs to an RHR valve.

The "A"

RHR loop was returned to service on February 8.

On February 10, the HPCT system was again removed from service in order to modify the hydraulic and electronic controls which set the HPCI system "ouick start" acceleration ramp.

The unit's fifth refueling outage began on February 13.

By February 18 reactor vessel head removal was complete and fuel off-load was begun on February 25.

At the end of the month, main turbine disassembly was in progress, unlatching of CRD blades was underway and the reactor recirculation system piping IHSI program had begun.