ML19343C045: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:.
{{#Wiki_filter:AVE 4 AGE DAIL) UN1( FUW6R LhVtl g
AVE 4 AGE DAIL) UN1( FUW6R LhVtl g                                     DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE FFSRUARY 10, 1981 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (213) 841-5022 MONTH     JANUARY 1981 DAY   AVERAGE DAILY POWER LEVEL             DAY         AVE. RAGE DAILY POWER LEVEL (MWE-NET)                                         (MWE-NET) 1                     998                   17                               392 2                     997                   18                               676 3                     898                   19                           1060 4                     1076                   20                       ,1013 5                     1084                   21                           1008 6                     672                   22                               473 7                       41                   23                               972 8                       71                   24                           1037 9                     370                   25                               910 10                     937                   26                           1063 11                     765                   27                           1073 12                     1055                   28                           1075 13                     1036                   29                           1072 14                     1080                   30                           1071 15                     1087                   31                               974 16                     1085                                             .
DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE FFSRUARY 10, 1981 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (213) 841-5022 MONTH JANUARY 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVE. RAGE DAILY POWER LEVEL (MWE-NET)
8102180$%
(MWE-NET) 1 998 17 392 2
997 18 676 3
898 19 1060 4
1076 20
,1013 5
1084 21 1008 6
672 22 473 7
41 23 972 8
71 24 1037 9
370 25 910 10 937 26 1063 11 765 27 1073 12 1055 28 1075 13 1036 29 1072 14 1080 30 1071 15 1087 31 974 16 1085 8102180$%


    ,                                  AVEQAGE DAILY UN!T POWER LEVEL DOCKET NO. 50 - 278 UNIT PEAC'H BOTTOM UNIT 3 DATE FEBRUARY 10, 1981 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH       JANUARY 1981 DAY     AVERAGE DAILY POWER LEVEL                     DAY         AVERAGE DAILY POWER L.EVEL (MWE-NET)                                         (MWE-NET) 1                           1060                     17                         1071 2                           1060                     18                         1073 3                           1061                     19                         1071 4                           1062                   20                     ,
AVEQAGE DAILY UN!T POWER LEVEL DOCKET NO. 50 - 278 UNIT PEAC'H BOTTOM UNIT 3 DATE FEBRUARY 10, 1981 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH JANUARY 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER L.EVEL (MWE-NET)
969 5                           1066                     21                         956 6                           1071                     22                         1060 7                           1065                     23                         1060 8                           1067                   24                         1053
(MWE-NET) 1 1060 17 1071 2
.          9                            1042                   25                         1049 t
1060 18 1073 3
,          10                               767                 26                         1055 l
1061 19 1071 4
j         11                           1015                   27                         1050 i         12                           1070                   28                         1056 13                           1071                   29                         1052 14                           1071                   30                         1052 15                           1064                   31                         1055 16                           -1071 se     ,4               *. g-     e v re-=                 --y
1062 20 969 5
                                                                    *F                                 g
1066 21 956 6
1071 22 1060 7
1065 23 1060 8
1067 24 1053 9
1042 25 1049 t
10 767 26 1055 l
j 11 1015 27 1050 i
12 1070 28 1056 13 1071 29 1052 14 1071 30 1052 15 1064 31 1055 16
-1071 se
,4 g-e v
re-=
--y
*F g


        .                              OPERATING 041A MEPUQ.
OPERATING 041A MEPUQ.
DOCKET NO. 50 - 277 OATE FEBRUARY 10, 1981 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.N.ALDEN E NGIN E E R -! N-CH A RG E NUCLEAR SECTION GENER ATION O!v!$ ION-NUCLE AR TELEPHONE (2151 841-5022 OPERATING STATUS
DOCKET NO. 50 - 277 OATE FEBRUARY 10, 1981 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.N.ALDEN E NGIN E E R -! N-CH A RG E NUCLEAR SECTION GENER ATION O!v!$ ION-NUCLE AR TELEPHONE (2151 841-5022 OPERATING STATUS
: 1. UNIT NAME: PEACH SOTTOM UNIT 2                                       l NOTES: THIS UNIT EXPERIENCE 0                         I
: 1. UNIT NAME: PEACH SOTTOM UNIT 2 l NOTES: THIS UNIT EXPERIENCE 0 I
                  ..._______          _____ . .______..._                g                                                       l
g l
: 2. REPORTING PERICO             JANUARY, 1981                           1           THREE MAJOR OUT AGES AND                   l
: 2. REPORTING PERICO JANUARY, 1981 1
__.        .___.. .. .. .___                l                                                       l
THREE MAJOR OUT AGES AND l
: 3. LICENSED THERMAL POWER (MWTil                                   3293 i           SIX MAJOR POWER REDUCTIONS                 l
l l
                                              .            ___ ._ _        l                                                       l 4 NAMEPLATE RATING (GROSS MWEls                                   1152 I                                                       I l                                                       l
: 3. LICENSED THERMAL POWER (MWTil 3293 i
: 5. DESIGN ELECTRICAL RATING INET "WEls                             1065 I                                                       l l                                                       l
SIX MAJOR POWER REDUCTIONS l
: 6. Max 1 MUM DEPENDABLE CAPACITY (GROSS MWEls 1098                       l                                                       l l                                                       1
l l
: 7. *AXIMUM DEPENDABLE CAPACITY (NET MWE):                         1051 1                                                       I
4 NAMEPLATE RATING (GROSS MWEls 1152 I
: 8. IF CH ANGE S GCCUR IN CAPACITY RATINGS (ITEMS NUM8ER 3 THROUGH 7) $1NCE LAST REPORT, GIVE RE ASON$r
I l
: 9. 9 0aER LEVEL TO WHICH RESTRICTED, IF ANY INET MWEls
l
: 10. SEASONS FOR RESTRICTIONS. IF ANYI THIS MONTH           YR-TO-DATE             CUMULATIVE
: 5. DESIGN ELECTRICAL RATING INET "WEls 1065 I
: 11. HCURS IN REPORTING PERIOD                                                   744                     744               57,672
l l
: 12. NUM8E4 0F HOURS RE ACTOR W AS CRITICAL                                   724.9                 724.9               43,277.4
l
: 13. REACT 04 RESERVE SHUTOOWN HOURS                                             0.0                     0.0                   0.0 14 HOUR $ GENERATOR ON-LINE                                                   692 8                 692.8               42,205.6
: 6. Max 1 MUM DEPENDABLE CAPACITY (GROSS MWEls 1098 l
: 15. UNIT RESERVE SHUTOOWN HOURS                                                 0.0                     0.0                   0.0
l l
: 16. GA055 THER*AL ENERGY GENERATED IMWH1                                 2.036,446             2,036,446           122.457,518
1
: 17. GROSS ELECTRIC AL ENERGY GENERATED (MWHI                               677,730             677,730             40,290.830
: 7. *AXIMUM DEPENDABLE CAPACITY (NET MWE):
: 18. NET ELECTRIC AL ENERGY GENER ATED (MWHI                                 655,816             655,816             38,615,480 19 UNIT SERVICE FACTOR                                                         93.1 ,
1051 1
93.1                   73.2
I 8.
: 20. UNIT AVAILABILITY SACTOR                                                   93.1                   93 1                   73.2
IF CH ANGE S GCCUR IN CAPACITY RATINGS (ITEMS NUM8ER 3 THROUGH 7) $1NCE LAST REPORT, GIVE RE ASON$r 0aER LEVEL TO WHICH RESTRICTED, IF ANY INET MWEls 9.
: 21. UNIT CAPACITY FACTOR IUSING MOC NET)                                       83.9                   83.9                   63.7
9
: 22. UNIT CAPACITY FACTOR (USING DER NET)                                       82.8                   82 8                   62.9
: 10. SEASONS FOR RESTRICTIONS. IF ANYI THIS MONTH YR-TO-DATE CUMULATIVE
: 23. UNIT FORCEO OUTAGE RATE                                                     6.9                     6.9                   6.1 26 SHUTOOWN5 $CHEDULEO OVER NEXT 6 MONTHS (TYPE, DATE, AND DUR ATION OF EACHis
: 11. HCURS IN REPORTING PERIOD 744 744 57,672
: 12. NUM8E4 0F HOURS RE ACTOR W AS CRITICAL 724.9 724.9 43,277.4
: 13. REACT 04 RESERVE SHUTOOWN HOURS 0.0 0.0 0.0 14 HOUR $ GENERATOR ON-LINE 692 8 692.8 42,205.6
: 15. UNIT RESERVE SHUTOOWN HOURS 0.0 0.0 0.0
: 16. GA055 THER*AL ENERGY GENERATED IMWH1 2.036,446 2,036,446 122.457,518
: 17. GROSS ELECTRIC AL ENERGY GENERATED (MWHI 677,730 677,730 40,290.830
: 18. NET ELECTRIC AL ENERGY GENER ATED (MWHI 655,816 655,816 38,615,480 19 UNIT SERVICE FACTOR 93.1 93.1 73.2
: 20. UNIT AVAILABILITY SACTOR 93.1 93 1 73.2
: 21. UNIT CAPACITY FACTOR IUSING MOC NET) 83.9 83.9 63.7
: 22. UNIT CAPACITY FACTOR (USING DER NET) 82.8 82 8 62.9
: 23. UNIT FORCEO OUTAGE RATE 6.9 6.9 6.1 26 SHUTOOWN5 $CHEDULEO OVER NEXT 6 MONTHS (TYPE, DATE, AND DUR ATION OF EACHis
: 25. IF SHUT 00wN AT END 08 REPORT PERIOD, ESTIMATED DATE OF STARTUP:
: 25. IF SHUT 00wN AT END 08 REPORT PERIOD, ESTIMATED DATE OF STARTUP:
: 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION 13                             FORECAST           ACH'IEVED INITI AL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
: 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION 13 FORECAST ACH'IEVED INITI AL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION qpaM c
_ __          qpaM
~
        ~     '
i c
i c   l   c
l


ppt ts f IM. P f* WEA!tl COCKET NO. 50 - 278 OATE FESRUARY 10, 1981 COMPLETED SY P'HILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERAT!DN O!VI510N-NUCLEAR TELEPHONE (215) 841-5022 CPERATING STATUS
ppt ts f IM. P f* WEA!tl COCKET NO. 50 - 278 OATE FESRUARY 10, 1981 COMPLETED SY P'HILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERAT!DN O!VI510N-NUCLEAR TELEPHONE (215) 841-5022 CPERATING STATUS
: 1. UNIT NAME: PFACH BOTTOM UNIT 3                                   l NOTES: THIS UNIT EXPERIENCE 0 NO                 l
: 1. UNIT NAME: PFACH BOTTOM UNIT 3 l NOTES: THIS UNIT EXPERIENCE 0 NO l
                      . . - - - . . - _ . . _ . .                        l                                                   l
l l
: 2. REPORTING PERIOD:           JANUARY, 1881                         1             MAJOR OUTAGES AND TWO I
: 2. REPORTING PERIOD:
'                                                                        I                                                   i
JANUARY, 1881 1
: 3. LICENSED THERMAL POWER (MWTit                             3293   l             M AJOR POWER REQUCTIONS l
MAJOR OUTAGES AND TWO I
l                                                 l
I i
: 4. NAMEPLATE RATING (G4055 MWEls                               1152   I                                                 l'
: 3. LICENSED THERMAL POWER (MWTit 3293 l
                                                          ....            l                                                  l S. DESIGN ELECTRICAL RATING INET MWE):                       1065   l                                                 l l                                                 l
M AJOR POWER REQUCTIONS l
: 6. Ma*1 MUM DEPENDABLE CAPACITY (GROSS MwEls 1098                     l                                                 1 l                                                 1
l l
: 7. MAXIMUM DEPENDABLE CAPACITY (NET MwElt                     1035   l                                                 l
: 4. NAMEPLATE RATING (G4055 MWEls 1152 I
l' l
l S. DESIGN ELECTRICAL RATING INET MWE):
1065 l
l l
l
: 6. Ma*1 MUM DEPENDABLE CAPACITY (GROSS MwEls 1098 l
1 l
1
: 7. MAXIMUM DEPENDABLE CAPACITY (NET MwElt 1035 l
l
: 8. IF CHANGE 5 OCCUR IN CAP ACITY RATINGS (ITFMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS
: 8. IF CHANGE 5 OCCUR IN CAP ACITY RATINGS (ITFMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS
: 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWEls
: 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWEls
: 10. REASONS FOR RESTRICTIONS. IF ANY:
: 10. REASONS FOR RESTRICTIONS. IF ANY:
THIS MONTH         YR-TO-DATE           CUMULATIVE
THIS MONTH YR-TO-DATE CUMULATIVE
: 11. HOUR S IN REPORTING PERIOD                                               744                   744 '           53,568
: 11. HOUR S IN REPORTING PERIOD 744 744 '
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL                                 744.0                 744.0           42,906.2
53,568
: 13. REACTOR RESERVE SHUTOOWN HOURS                                           0.0                 0.0                 0.0 14 HOURS GENEPATOR ON-LINE                                                 744.0                 744.0           41,768.8
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 744.0 42,906.2
: 15. UNIT RESERVE SHUTCOWN HOURS                                             0.0                   0.0                 0.0
: 13. REACTOR RESERVE SHUTOOWN HOURS 0.0 0.0 0.0 14 HOURS GENEPATOR ON-LINE 744.0 744.0 41,768.8
: 16. GR055 THEkMAL ENERGY GENERATED (MWHI                             2,399,626           2,399,626         119.242,575
: 15. UNIT RESERVE SHUTCOWN HOURS 0.0 0.0 0.0
: 17. GROSS ELECTRIC AL ENERGY GENER ATED (MWH)                           801,660             801,660         38,903,700
: 16. GR055 THEkMAL ENERGY GENERATED (MWHI 2,399,626 2,399,626 119.242,575
: 18. NET ELECTRIC AL ENERGY GENERATED (MWHI                               776,964             776,984         37,355,627
: 17. GROSS ELECTRIC AL ENERGY GENER ATED (MWH) 801,660 801,660 38,903,700
: 19. UNIT SERVICE FACTOR                                                   100.0                 100.0               78.0
: 18. NET ELECTRIC AL ENERGY GENERATED (MWHI 776,964 776,984 37,355,627
: 20. UNIT AVAILABILITY FACTOR                                               100.0                 100.0               78.0
: 19. UNIT SERVICE FACTOR 100.0 100.0 78.0
: 21. UNIT CAPACITY FACTOR (USING MDC NET)                                   100.9                 100.9               67.4
: 20. UNIT AVAILABILITY FACTOR 100.0 100.0 78.0
: 22. UNIT CAPACITY FACTOR (USING DER NET)                                   98.1.                 98.1               65.5
: 21. UNIT CAPACITY FACTOR (USING MDC NET) 100.9 100.9 67.4
: 23. UNIT FORCED OUTAGE R ATE                                                 0.0                   0.0                 74
: 22. UNIT CAPACITY FACTOR (USING DER NET) 98.1.
98.1 65.5
: 23. UNIT FORCED OUTAGE R ATE 0.0 0.0 74
: 24. SHUTOOwNS SCHEDULED OVER NEXT 6 MONTH 5 (TYPE, DATE. AND DUR ATION OF EACHl REFUELING / MAINTENANCE, 3/7/81, TWENTYTHREE WEEKS
: 24. SHUTOOwNS SCHEDULED OVER NEXT 6 MONTH 5 (TYPE, DATE. AND DUR ATION OF EACHl REFUELING / MAINTENANCE, 3/7/81, TWENTYTHREE WEEKS
: 25. IF SHUTCowN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP                                       ,
: 25. IF SHUTCowN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP
: 24. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):                           FORECAST       ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION y,   g. e a em .       W 8upuM             O ' " h
: 24. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION y,
g.
e a em.
W 8upuM O ' " h


0 UNIT SHUTDOWNS AND F0WE2 CEDUCTIONS                                   DOCRET NO. 50 - 27T                                         -
0 UNIT SHUTDOWNS AND F0WE2 CEDUCTIONS DOCRET NO. 50 - 27T UNIT NAME PEACH BOTTOM UNIT 2 D ATE FE BRUARY 10, 1981 REPORT MONTH JANUARY, 1981 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN E NGINE E R-IN-C H ARGE NUCLEAR SECTION GE NE R A T ION DI VI slON-NUCL E A R e
UNIT NAME PEACH BOTTOM UNIT 2 D ATE FE BRUARY 10, 1981
TELEPHONE 12158 841-5022
* REPORT MONTH       JANUARY, 1981                             COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN E NGINE E R-IN-C H ARGE NUCLEAR SECTION e                                                                                                                                GE NE R A T ION DI VI slON-NUCL E A R TELEPHONE 12158 841-5022
-~~~~~~
                                                                                                                                      -~~~~~~
-- =-
                                                                                          -- =-                        _----                    -
6 l
6         l         l         l         I         l METHOO OF l LICENSEE I SYSTFMICOMPONENil C AUSE AND CORREC TIVE l         l TYPElDURATIONlRE ASONISHUITING DOWN1               EVENT     l CODE l         CODE 1               ACTION TO g
l l
No.1 CATE l .._till (HOURSal 128 i REACTOR E3) l REPORT e 1 (4) l                               (53 l PREVENT RECURRENCE 1         I         I         I         I               I               I           I               i 1 1 810102 1 5 1 000.0           i     H   l       4       i NA             l RC l 222222 I LOAD DROP FOR ROD PATTERN ADJUSTMENT.
I l METHOO OF l LICENSEE I SYSTFMICOMPONENil C AUSE AND CORREC TIVE l
O           I         I         i         1         I               I               I           I               i 2 1 810106 l F l 020.1             1     A   l       1       i NA             l HA l VALVEX l EHC OIL LEAKS ON                     . 83 AND #4 TURBINE CONTROL 1         I         I         i         1               1               l           l               l   VALVES.
l TYPElDURATIONlRE ASONISHUITING DOWN1 EVENT l CODE l CODE 1 ACTION TO No.1 CATE l till (HOURSal 128 i REACTOR E3) l REPORT e 1 (4) l (53 l PREVENT RECURRENCE g
o         I         1         1         i         1               I               i           i               I 3 I 81010s i F l 025.0             l     A   I       2       i Na             l C8 I MECFUN l 28 RECIRCUL AT ION M-G SET FLUIG DRIVE I       l         l         l         I               I               l             l               l INTERNAL LIN44GE REPAIR.
1 I
  =           l       l                               I               I 1        1                                          I             i               1 4 1 810110 l $ 1 000.0           i     H I         4       l   'NA         l RC l 22Z222 i LOAD DROP FOR ROD PATTERN ADJUSTMENT.
I I
I         i         1         I         i               1               I           i               I                                                                 ~
I I
w      5 1 810117 l F l 000.0           l     A   l       4       l NA             l 18 l INSTRU l LOAD DROP FOR ROD PATTERN ADJUSTMENT AND l         l         l         l         l   .          l               l             l I
I I
l 2D MAIN STEAM LINE RAD MONITOR REPAIR.
i 1 1 810102 1 5 1 000.0 i
I         I         I         I               I               I           I               I o       6 I 810120 1 5 1 000.0           i     H I       4       l     NA         I RC l ZzzzzZ l LOAD DROP FOR ROD PATTERN ADJUSTMENT.
H l
I         I         I         I         I               I               I           I               i 7l 810122 i F l 006 1 l                 A   1       1       1 NA             l HA l VALVEX l s2 TUR8INE CONTROL VALVE SERYO F AILURE.
4 i NA l RC l 222222 I LOAD DROP FOR ROD PATTERN ADJUSTMENT.
e         i         I         I         I         I               I               I           I               i 8 I 810125 i S I 000.0 i                 H I       4       l NA             l RC l ZZZZll i LOAD DROP FOR ROD PATTERN ADJUSTMENT.
O I
1         I         i         1         l               I               I           I               I o     9 1 810131 1 Sl 000.0             l     H I       4       l NA             I RC l ZZZZZ2 l LOAD DROP FOR ROD PATTERN ADJUSTME NT.
I i
I         I         I =- - I           i               i               1           i               i l         l         l $1 2 l           l               l               l           l               l
1 I
* O e
I I
s p             (1)                           (2)                                                           (3)                               843 F - FORCED               REASON                                                       METHOD y     5 - SCHE DUL ED EXHIBIT G - INSTRUCTIONS A - EQUIPMENT FAILURE (EXPLAIN)                             1 - MANUAL                             FOR PREPAR ATION OF DATA 8 - MAINTENANCE OR TEST                                     2 - MANUAL SCRAM.                     ENTRY SHEETS FOR LICENSEE C - REFUELING                                               3 - AUTOMATIC SCRAM.                   EVENT REPORT (LERI D - REGULATORY RESTRICTION                                   4 - OT HER (EXPL AINI                     FILE ( NUR E G-01618 E - OPERATOR TRAINING + LICENSE EXANINATION F - ADMINISTRATIVE                                                                                           (5)
I i
G - OPER A TION AL ERROR (EXPLAINI H - OTHERIEXPLAINI                                                                                 EXHIBIT I - SAME SOURCE
. 83 AND #4 TURBINE CONTROL 2 1 810106 l F l 020.1 1
A l
1 i NA l HA l VALVEX l EHC OIL LEAKS ON 1
I I
i 1
1 l
l l
VALVES.
o I
1 1
i 1
I i
i I
3 I 81010s i F l 025.0 l
A I
2 i Na l C8 I MECFUN l 28 RECIRCUL AT ION M-G SET FLUIG DRIVE I
l l
l I
I l
l l INTERNAL LIN44GE REPAIR.
=
l l
1 1
I I
I i
1 4 1 810110 l $ 1 000.0 i
H I 4
l
'NA l RC l 22Z222 i LOAD DROP FOR ROD PATTERN ADJUSTMENT.
~
I i
1 I
i 1
I i
I w
5 1 810117 l F l 000.0 l
A l
4 l NA l 18 l INSTRU l LOAD DROP FOR ROD PATTERN ADJUSTMENT AND l
l l
l l
l l
l l 2D MAIN STEAM LINE RAD MONITOR REPAIR.
I I
I I
I I
I I
I o
6 I 810120 1 5 1 000.0 i
H I 4
l NA I RC l ZzzzzZ l LOAD DROP FOR ROD PATTERN ADJUSTMENT.
I I
I I
I I
I I
i 7l 810122 i F l 006 1 l A
1 1
1 NA l HA l VALVEX l s2 TUR8INE CONTROL VALVE SERYO F AILURE.
e i
I I
I I
I I
I i
8 I 810125 i S I 000.0 i
H I 4
l NA l RC l ZZZZll i LOAD DROP FOR ROD PATTERN ADJUSTMENT.
1 I
i 1
l I
I I
I o
9 1 810131 1 Sl 000.0 l
H I 4
l NA I RC l ZZZZZ2 l LOAD DROP FOR ROD PATTERN ADJUSTME NT.
I I
I =-
- I i
i 1
i i
l l
l $1 2 l l
l l
l l
O e
s p
(1)
(2)
(3) 843 F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS y
5 - SCHE DUL ED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPAR ATION OF DATA 8 - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LERI D - REGULATORY RESTRICTION 4 - OT HER (EXPL AINI FILE ( NUR E G-01618 E - OPERATOR TRAINING + LICENSE EXANINATION F - ADMINISTRATIVE (5)
G - OPER A TION AL ERROR (EXPLAINI H - OTHERIEXPLAINI EXHIBIT I - SAME SOURCE


o UNIT SH91 downs AND POWER REDUCTIONS                                       DOCKET NO. 50 - 276 UNIT NAME PEACH BOTTON UNIT 3 OATE FEBRUARY 10, 1981 REPOR T MONTH   JANUARY, leEl                                 COMPLETED BY PHILADELPHIA ELECTR IC COMP ANY.
o UNIT SH91 downs AND POWER REDUCTIONS DOCKET NO. 50 - 276 UNIT NAME PEACH BOTTON UNIT 3 OATE FEBRUARY 10, 1981 REPOR T MONTH JANUARY, leEl COMPLETED BY PHILADELPHIA ELECTR IC COMP ANY.
* W.M.ALDEN E N G I NE E R-IN-C H A RG E NUCLEAR SECTION GENER ATION DIVISION-NUCLE AR TELEPHONE (2153 841-5022
W.M.ALDEN E N G I NE E R-IN-C H A RG E NUCLEAR SECTION GENER ATION DIVISION-NUCLE AR TELEPHONE (2153 841-5022
            =----    .        _- . .................-                    _. ---- -..........--
=----
i           l   l             l             l METHOD OF l LICENSEE 15YSTEMICOMPONENTl CAUSE AND CORRECTIVE l           1TVPEl0URATIONlREA50N15 HUTTING DOWNI                   EVENT           l CODE I         CODE l       ACTION TO NO.B   OATE i till thodR5il               (2) 1 REACIOR 838 l REPORT s 1                       (4) l ISI l PREVENT RECURRENCE I           i   l             I             I             I                       I         I             i 1 1 810109 l 5 1 000.0             l       H I           4     l NA                   l RC l ZZZZZZ l LOAD DROP FOR ROD PATTERN ADJUSIME NT.
i l
I           I   l             l             1             1 I         I             I 2l 810120 1 F l 000.0               1       A     l       4     i NA                   l HF l HTENCH l LOAD OROP TO REPATR A-1 AND 8-1 WATER l           !    l             l             l             l                       l         l             l   B0xES.
l l
1           I   I     -
l METHOD OF l LICENSEE 15YSTEMICOMPONENTl CAUSE AND CORRECTIVE l
1              I             I                       I         I             I I           I   I -           1             I             I                       I         I             I L
1TVPEl0URATIONlREA50N15 HUTTING DOWNI EVENT l CODE I CODE l ACTION TO NO.B OATE i till thodR5il (2) 1 REACIOR 838 l REPORT s 1 (4) l ISI l PREVENT RECURRENCE I
til                             (2)                                                                   (3)                           (4)
i l
F - FORCED           REASON                                                                   METHOD                         ERHIBIT G - INSTRUCTIONS 5 - SCHEDULLD         A - EQUIPMENT FAILURE (EXPLAIN)                                           1 - MANUAL                     F OR PREPAR ATION OF DATA 8 - MAINTENANCE OR TEST                                                   2 - NANUAL SCRAM.               ENTRY SHEETS FOR LICENSEE C - REFUELING                                                             3 - AUTOMATIC SCRAM.           EVENT REPORT (LERI D - REGULATORY RESTRICTION                                               4 - OTHE   R (EXPLAINI             FILE INUREG-0161)
I I
E - OPERATOR TRAINING + LICENSE EXANINATION F - ADMINISTRATIVE                                                                                                   (5)
I I
G - OPERATIONAL ERROR (EXPLAINI H - OTHERRENPLAINI                                                                                       EXHIBIT I - SAME SOURCE 0
I i
1 1 810109 l 5 1 000.0 l
H I 4
l NA l RC l ZZZZZZ l LOAD DROP FOR ROD PATTERN ADJUSIME NT.
I I
l l
1 1
I I
I 2l 810120 1 F l 000.0 1
A l
4 i NA l HF l HTENCH l LOAD OROP TO REPATR A-1 AND 8-1 WATER l
l l
l l
l l
l B0xES.
1 I
I 1
I I
I I
I I
I I -
1 I
I I
I I
L til (2)
(3)
(4)
F - FORCED REASON METHOD ERHIBIT G - INSTRUCTIONS 5 - SCHEDULLD A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL F OR PREPAR ATION OF DATA 8 - MAINTENANCE OR TEST 2 - NANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LERI D - REGULATORY RESTRICTION 4 - OTHE R (EXPLAINI FILE INUREG-0161)
E - OPERATOR TRAINING + LICENSE EXANINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAINI H - OTHERRENPLAINI EXHIBIT I - SAME SOURCE 0


                    ~-
~-
Docket No. 50-277 Attachment to Monthly Operating Report For January,1981 f
Docket No. 50-277 Attachment to Monthly Operating Report For January,1981 f
          ,                                        RDTELING INFORMATION 1,     Name of facility:
RDTELING INFORMATION 1,
Peach Bottom Unit 2
Name of facility:
: 2.       Scheduled date for next refueling shutdown:
Peach Bottom Unit 2 2.
January 2, 1982 3       Scheduled date for restart following refueling:
Scheduled date for next refueling shutdown:
February 13, 1982 14       Vill refueling or resumption of operation thereafter require a technical specification charige or other license amendment?
January 2, 1982 3
Scheduled date for restart following refueling:
February 13, 1982 14 Vill refueling or resumption of operation thereafter require a technical specification charige or other license amendment?
Yes.
Yes.
                                                              ,.        e If answer is yes, what,'in general, will these be?
e 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 Scheduled date(s) for submitting proposed licensing action and supporting information:
November 13, 1981
November 13, 1981 6.
: 6.       Important licensing considerations ass,ociated with refueling, e.g. ,
Important licensing considerations ass,ociated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance analysis methods, signiricant changes in fuel design, new operating procedures:
new or different fuel design or supplier, unreviewed design or performance analysis methods, signiricant changes in fuel design, new operating procedures:
None expected.
None expected.
7         The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools                                   -
7 The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools a
Core - 7614 Fuel Assemblies b   Fuel Pool - 910 Fuel Assemblies
Core - 7614 Fuel Assemblies b
: 8.       The present licensed spent fuel pool storage capacity and the size of any increase in licensed storego capacity that has been requested or is planned, in number of fuel assemblies:
Fuel Pool - 910 Fuel Assemblies 8.
The spent fuel pool stcrage capacity has been relicensed for 2816 fuel assemblies.                                                   ,
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storego capacity that has been requested or is planned, in number of fuel assemblies:
,            9         The projected date of the last refueling that can be discharged to the spent fuel pool assuning the present licensed capacity.
The spent fuel pool stcrage capacity has been relicensed for 2816 fuel assemblies.
September, 1990
9 The projected date of the last refueling that can be discharged to the spent fuel pool assuning the present licensed capacity.
..                      . . . .                                                                n .
September, 1990 n.
r w . -     --      - - - -
r w. -
-e


Dockot No. 50-278 Attachment to Monthly Operating Report For Januarv,1981l annsING UGGMATICH i
Dockot No. 50-278 Attachment to Monthly Operating Report For Januarv,1981l annsING UGGMATICH i
: 1. Name of facility:
1.
Peach Bottom Unit 3
Name of facility:
: 2. Scheduled date for next refueling shutdowns March 7, 1981 3     Scheduled date for restart l'ollowing refueling:
Peach Bottom Unit 3 2.
August 1h, 1981
Scheduled date for next refueling shutdowns March 7, 1981 3
: h. Will reiteling or. resumption of operation thereafter require a technical specification changei or other license amendment?
Scheduled date for restart l'ollowing refueling:
Yes.                         ,
August 1h, 1981 h.
Will reiteling or. resumption of operation thereafter require a technical specification changei or other license amendment?
Yes.
If answer is yise,' :<nat, in general, will these be?
If answer is yise,' :<nat, in general, will these be?
Technical specification changes to acconnodate reload IVel.
Technical specification changes to acconnodate reload IVel.
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 l                             supporting information:
5 Scheduled date(s) for submitting proposed licensing action and l
March 6, 1981
supporting information:
: 6. Important licensing considerations assooisted with refueling, e.g.,
March 6, 1981 6.
Important licensing considerations assooisted with refueling, e.g.,
new or fifferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
new or fifferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
Ncne expected.                         ,
Ncne expected.
: 7. Thenumberoffuelassemblies(a)inthecoreand(b)inthespent fuel storage Pools (a) Core - 76h Fuel Aseeablies (b) Fuel Pool - 712 Irradiated Fuel Assemblies
7.
: 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has bee-1 requested or is planned, in number of fuel assemblies:
Thenumberoffuelassemblies(a)inthecoreand(b)inthespent fuel storage Pools (a) Core - 76h Fuel Aseeablies (b) Fuel Pool - 712 Irradiated Fuel Assemblies 8.
l The spent fusi pool storage capacity has been relicensed for 2816 fuel assemblies.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has bee-1 requested l
l                         9   The projected date of the last refueling that can be discharged to l    c                          the spent fuel pool assuming the present licensed capacity:
or is planned, in number of fuel assemblies:
  .                            September, 1991 l
The spent fusi pool storage capacity has been relicensed for 2816 fuel assemblies.
l 9
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
l c
September, 1991 l


                    .                        PE A C61 110TTor' AT0" f C POW 4 "TATim N ARRATIVE SUM"ARY nF OPEP ATI!!G EX PERTMICES JAMUARY 1991 a
PE A C61 110TTor' AT0" f C POW 4 "TATim N ARRATIVE SUM"ARY nF OPEP ATI!!G EX PERTMICES JAMUARY 1991 a
UNIT 2 OPERATIONS A load reduction was taken at the beginning of the month to accommodate a control rod pattern adjustment. On January 6, the unit was removed from service to accommodate repair of ar.
UNIT 2 OPERATIONS A load reduction was taken at the beginning of the month to accommodate a control rod pattern adjustment.
electro-hydraulic control system fluid leak. During the outage tests were performed on the scram discharge volume monitoring sy: tem. During the return to service on January 7, a bearing failed in the 2B recirculation pump hydraulic coupling control system. On January 10, a load reduction was taken to accommodate' a control rod pattern adjustment. On January 13, an orderly shutdown wss conducted until the E-3 diesel generator breaker
On January 6, the unit was removed from service to accommodate repair of ar.
  ;                        could be replaced with a spare and successfully tested. C, j                         January 17, a load reduction was taken to accommodate a control rod pattern adjustment and unexpected repairs to the 2D main steam line radiation =onitor. On January 20, a load drop was taken to accommodate a control rod adjustment. On January 22, the unit was removed from service to accommodate repairs to d2 turbine control valve servo mechanism. Additionaly load drops were taken to accommodate control rod pattern adjustments.
electro-hydraulic control system fluid leak.
Significant safety related maintenance performed during the month was: RCIC flow transmitter for full scale failure, 2B recirculation pump MG set hudraulic coupling scoop tube control failure, E-3 diesel generator breaker failure to close, Group III isolation relay failure, and 2D main steam line radiation monitor up scale failure due to a grounded cable.                       ,
During the outage tests were performed on the scram discharge volume monitoring sy: tem.
During the return to service on January 7, a bearing failed in the 2B recirculation pump hydraulic coupling control system.
On January 10, a load reduction was taken to accommodate' a control rod pattern adjustment.
On January 13, an orderly shutdown wss conducted until the E-3 diesel generator breaker could be replaced with a spare and successfully tested.
C, j
January 17, a load reduction was taken to accommodate a control rod pattern adjustment and unexpected repairs to the 2D main steam line radiation =onitor.
On January 20, a load drop was taken to accommodate a control rod adjustment.
On January 22, the unit was removed from service to accommodate repairs to d2 turbine control valve servo mechanism.
Additionaly load drops were taken to accommodate control rod pattern adjustments.
Significant safety related maintenance performed during the month was: RCIC flow transmitter for full scale failure, 2B recirculation pump MG set hudraulic coupling scoop tube control failure, E-3 diesel generator breaker failure to close, Group III isolation relay failure, and 2D main steam line radiation monitor up scale failure due to a grounded cable.
UNIT 1 OPERATION The Unit operated through the month at full power except for a brief load drop on January 10 to accommodate a control rod pattern adjustment and January 20, to accommodate repair of tube leaks in the A and B condensers.
UNIT 1 OPERATION The Unit operated through the month at full power except for a brief load drop on January 10 to accommodate a control rod pattern adjustment and January 20, to accommodate repair of tube leaks in the A and B condensers.
n Significant sa'fety related maintenance performed during the month was: 3b core spray pump breaker for charging pump failure and l                         HPCI outboard bearing leak.
n Significant sa'fety related maintenance performed during the month was: 3b core spray pump breaker for charging pump failure and l
HPCI outboard bearing leak.
l l
l l
l I
l I
                                                                                                  - , - ,  m.~ .}}
m.~
.}}

Latest revision as of 12:22, 24 December 2024

Monthly Operating Repts for Jan 1981
ML19343C045
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 02/10/1981
From: Alden W
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19343C042 List:
References
NUDOCS 8102180526
Download: ML19343C045 (9)


Text

AVE 4 AGE DAIL) UN1( FUW6R LhVtl g

DOCKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE FFSRUARY 10, 1981 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (213) 841-5022 MONTH JANUARY 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVE. RAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 998 17 392 2

997 18 676 3

898 19 1060 4

1076 20

,1013 5

1084 21 1008 6

672 22 473 7

41 23 972 8

71 24 1037 9

370 25 910 10 937 26 1063 11 765 27 1073 12 1055 28 1075 13 1036 29 1072 14 1080 30 1071 15 1087 31 974 16 1085 8102180$%

AVEQAGE DAILY UN!T POWER LEVEL DOCKET NO. 50 - 278 UNIT PEAC'H BOTTOM UNIT 3 DATE FEBRUARY 10, 1981 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH JANUARY 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER L.EVEL (MWE-NET)

(MWE-NET) 1 1060 17 1071 2

1060 18 1073 3

1061 19 1071 4

1062 20 969 5

1066 21 956 6

1071 22 1060 7

1065 23 1060 8

1067 24 1053 9

1042 25 1049 t

10 767 26 1055 l

j 11 1015 27 1050 i

12 1070 28 1056 13 1071 29 1052 14 1071 30 1052 15 1064 31 1055 16

-1071 se

,4 g-e v

re-=

--y

  • F g

OPERATING 041A MEPUQ.

DOCKET NO. 50 - 277 OATE FEBRUARY 10, 1981 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.N.ALDEN E NGIN E E R -! N-CH A RG E NUCLEAR SECTION GENER ATION O!v!$ ION-NUCLE AR TELEPHONE (2151 841-5022 OPERATING STATUS

1. UNIT NAME: PEACH SOTTOM UNIT 2 l NOTES: THIS UNIT EXPERIENCE 0 I

g l

2. REPORTING PERICO JANUARY, 1981 1

THREE MAJOR OUT AGES AND l

l l

3. LICENSED THERMAL POWER (MWTil 3293 i

SIX MAJOR POWER REDUCTIONS l

l l

4 NAMEPLATE RATING (GROSS MWEls 1152 I

I l

l

5. DESIGN ELECTRICAL RATING INET "WEls 1065 I

l l

l

6. Max 1 MUM DEPENDABLE CAPACITY (GROSS MWEls 1098 l

l l

1

7. *AXIMUM DEPENDABLE CAPACITY (NET MWE):

1051 1

I 8.

IF CH ANGE S GCCUR IN CAPACITY RATINGS (ITEMS NUM8ER 3 THROUGH 7) $1NCE LAST REPORT, GIVE RE ASON$r 0aER LEVEL TO WHICH RESTRICTED, IF ANY INET MWEls 9.

9

10. SEASONS FOR RESTRICTIONS. IF ANYI THIS MONTH YR-TO-DATE CUMULATIVE
11. HCURS IN REPORTING PERIOD 744 744 57,672
12. NUM8E4 0F HOURS RE ACTOR W AS CRITICAL 724.9 724.9 43,277.4
13. REACT 04 RESERVE SHUTOOWN HOURS 0.0 0.0 0.0 14 HOUR $ GENERATOR ON-LINE 692 8 692.8 42,205.6
15. UNIT RESERVE SHUTOOWN HOURS 0.0 0.0 0.0
16. GA055 THER*AL ENERGY GENERATED IMWH1 2.036,446 2,036,446 122.457,518
17. GROSS ELECTRIC AL ENERGY GENERATED (MWHI 677,730 677,730 40,290.830
18. NET ELECTRIC AL ENERGY GENER ATED (MWHI 655,816 655,816 38,615,480 19 UNIT SERVICE FACTOR 93.1 93.1 73.2
20. UNIT AVAILABILITY SACTOR 93.1 93 1 73.2
21. UNIT CAPACITY FACTOR IUSING MOC NET) 83.9 83.9 63.7
22. UNIT CAPACITY FACTOR (USING DER NET) 82.8 82 8 62.9
23. UNIT FORCEO OUTAGE RATE 6.9 6.9 6.1 26 SHUTOOWN5 $CHEDULEO OVER NEXT 6 MONTHS (TYPE, DATE, AND DUR ATION OF EACHis
25. IF SHUT 00wN AT END 08 REPORT PERIOD, ESTIMATED DATE OF STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION 13 FORECAST ACH'IEVED INITI AL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION qpaM c

~

i c

l

ppt ts f IM. P f* WEA!tl COCKET NO. 50 - 278 OATE FESRUARY 10, 1981 COMPLETED SY P'HILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE NUCLEAR SECTION GENERAT!DN O!VI510N-NUCLEAR TELEPHONE (215) 841-5022 CPERATING STATUS

1. UNIT NAME: PFACH BOTTOM UNIT 3 l NOTES: THIS UNIT EXPERIENCE 0 NO l

l l

2. REPORTING PERIOD:

JANUARY, 1881 1

MAJOR OUTAGES AND TWO I

I i

3. LICENSED THERMAL POWER (MWTit 3293 l

M AJOR POWER REQUCTIONS l

l l

4. NAMEPLATE RATING (G4055 MWEls 1152 I

l' l

l S. DESIGN ELECTRICAL RATING INET MWE):

1065 l

l l

l

6. Ma*1 MUM DEPENDABLE CAPACITY (GROSS MwEls 1098 l

1 l

1

7. MAXIMUM DEPENDABLE CAPACITY (NET MwElt 1035 l

l

8. IF CHANGE 5 OCCUR IN CAP ACITY RATINGS (ITFMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWEls
10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

11. HOUR S IN REPORTING PERIOD 744 744 '

53,568

12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 744.0 42,906.2
13. REACTOR RESERVE SHUTOOWN HOURS 0.0 0.0 0.0 14 HOURS GENEPATOR ON-LINE 744.0 744.0 41,768.8
15. UNIT RESERVE SHUTCOWN HOURS 0.0 0.0 0.0
16. GR055 THEkMAL ENERGY GENERATED (MWHI 2,399,626 2,399,626 119.242,575
17. GROSS ELECTRIC AL ENERGY GENER ATED (MWH) 801,660 801,660 38,903,700
18. NET ELECTRIC AL ENERGY GENERATED (MWHI 776,964 776,984 37,355,627
19. UNIT SERVICE FACTOR 100.0 100.0 78.0
20. UNIT AVAILABILITY FACTOR 100.0 100.0 78.0
21. UNIT CAPACITY FACTOR (USING MDC NET) 100.9 100.9 67.4
22. UNIT CAPACITY FACTOR (USING DER NET) 98.1.

98.1 65.5

23. UNIT FORCED OUTAGE R ATE 0.0 0.0 74
24. SHUTOOwNS SCHEDULED OVER NEXT 6 MONTH 5 (TYPE, DATE. AND DUR ATION OF EACHl REFUELING / MAINTENANCE, 3/7/81, TWENTYTHREE WEEKS
25. IF SHUTCowN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP
24. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION y,

g.

e a em.

W 8upuM O ' " h

0 UNIT SHUTDOWNS AND F0WE2 CEDUCTIONS DOCRET NO. 50 - 27T UNIT NAME PEACH BOTTOM UNIT 2 D ATE FE BRUARY 10, 1981 REPORT MONTH JANUARY, 1981 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN E NGINE E R-IN-C H ARGE NUCLEAR SECTION GE NE R A T ION DI VI slON-NUCL E A R e

TELEPHONE 12158 841-5022

-~~~~~~

-- =-

6 l

l l

I l METHOO OF l LICENSEE I SYSTFMICOMPONENil C AUSE AND CORREC TIVE l

l TYPElDURATIONlRE ASONISHUITING DOWN1 EVENT l CODE l CODE 1 ACTION TO No.1 CATE l till (HOURSal 128 i REACTOR E3) l REPORT e 1 (4) l (53 l PREVENT RECURRENCE g

1 I

I I

I I

I I

i 1 1 810102 1 5 1 000.0 i

H l

4 i NA l RC l 222222 I LOAD DROP FOR ROD PATTERN ADJUSTMENT.

O I

I i

1 I

I I

I i

. 83 AND #4 TURBINE CONTROL 2 1 810106 l F l 020.1 1

A l

1 i NA l HA l VALVEX l EHC OIL LEAKS ON 1

I I

i 1

1 l

l l

VALVES.

o I

1 1

i 1

I i

i I

3 I 81010s i F l 025.0 l

A I

2 i Na l C8 I MECFUN l 28 RECIRCUL AT ION M-G SET FLUIG DRIVE I

l l

l I

I l

l l INTERNAL LIN44GE REPAIR.

=

l l

1 1

I I

I i

1 4 1 810110 l $ 1 000.0 i

H I 4

l

'NA l RC l 22Z222 i LOAD DROP FOR ROD PATTERN ADJUSTMENT.

~

I i

1 I

i 1

I i

I w

5 1 810117 l F l 000.0 l

A l

4 l NA l 18 l INSTRU l LOAD DROP FOR ROD PATTERN ADJUSTMENT AND l

l l

l l

l l

l l 2D MAIN STEAM LINE RAD MONITOR REPAIR.

I I

I I

I I

I I

I o

6 I 810120 1 5 1 000.0 i

H I 4

l NA I RC l ZzzzzZ l LOAD DROP FOR ROD PATTERN ADJUSTMENT.

I I

I I

I I

I I

i 7l 810122 i F l 006 1 l A

1 1

1 NA l HA l VALVEX l s2 TUR8INE CONTROL VALVE SERYO F AILURE.

e i

I I

I I

I I

I i

8 I 810125 i S I 000.0 i

H I 4

l NA l RC l ZZZZll i LOAD DROP FOR ROD PATTERN ADJUSTMENT.

1 I

i 1

l I

I I

I o

9 1 810131 1 Sl 000.0 l

H I 4

l NA I RC l ZZZZZ2 l LOAD DROP FOR ROD PATTERN ADJUSTME NT.

I I

I =-

- I i

i 1

i i

l l

l $1 2 l l

l l

l l

O e

s p

(1)

(2)

(3) 843 F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS y

5 - SCHE DUL ED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPAR ATION OF DATA 8 - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LERI D - REGULATORY RESTRICTION 4 - OT HER (EXPL AINI FILE ( NUR E G-01618 E - OPERATOR TRAINING + LICENSE EXANINATION F - ADMINISTRATIVE (5)

G - OPER A TION AL ERROR (EXPLAINI H - OTHERIEXPLAINI EXHIBIT I - SAME SOURCE

o UNIT SH91 downs AND POWER REDUCTIONS DOCKET NO. 50 - 276 UNIT NAME PEACH BOTTON UNIT 3 OATE FEBRUARY 10, 1981 REPOR T MONTH JANUARY, leEl COMPLETED BY PHILADELPHIA ELECTR IC COMP ANY.

W.M.ALDEN E N G I NE E R-IN-C H A RG E NUCLEAR SECTION GENER ATION DIVISION-NUCLE AR TELEPHONE (2153 841-5022

=----

i l

l l

l METHOD OF l LICENSEE 15YSTEMICOMPONENTl CAUSE AND CORRECTIVE l

1TVPEl0URATIONlREA50N15 HUTTING DOWNI EVENT l CODE I CODE l ACTION TO NO.B OATE i till thodR5il (2) 1 REACIOR 838 l REPORT s 1 (4) l ISI l PREVENT RECURRENCE I

i l

I I

I I

I i

1 1 810109 l 5 1 000.0 l

H I 4

l NA l RC l ZZZZZZ l LOAD DROP FOR ROD PATTERN ADJUSIME NT.

I I

l l

1 1

I I

I 2l 810120 1 F l 000.0 1

A l

4 i NA l HF l HTENCH l LOAD OROP TO REPATR A-1 AND 8-1 WATER l

l l

l l

l l

l B0xES.

1 I

I 1

I I

I I

I I

I I -

1 I

I I

I I

L til (2)

(3)

(4)

F - FORCED REASON METHOD ERHIBIT G - INSTRUCTIONS 5 - SCHEDULLD A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL F OR PREPAR ATION OF DATA 8 - MAINTENANCE OR TEST 2 - NANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LERI D - REGULATORY RESTRICTION 4 - OTHE R (EXPLAINI FILE INUREG-0161)

E - OPERATOR TRAINING + LICENSE EXANINATION F - ADMINISTRATIVE (5)

G - OPERATIONAL ERROR (EXPLAINI H - OTHERRENPLAINI EXHIBIT I - SAME SOURCE 0

~-

Docket No. 50-277 Attachment to Monthly Operating Report For January,1981 f

RDTELING INFORMATION 1,

Name of facility:

Peach Bottom Unit 2 2.

Scheduled date for next refueling shutdown:

January 2, 1982 3

Scheduled date for restart following refueling:

February 13, 1982 14 Vill refueling or resumption of operation thereafter require a technical specification charige or other license amendment?

Yes.

e 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:

November 13, 1981 6.

Important licensing considerations ass,ociated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, signiricant changes in fuel design, new operating procedures:

None expected.

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

Core - 7614 Fuel Assemblies b

Fuel Pool - 910 Fuel Assemblies 8.

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

The spent fuel pool stcrage 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 assuning the present licensed capacity.

September, 1990 n.

r w. -

-e

Dockot No. 50-278 Attachment to Monthly Operating Report For Januarv,1981l annsING UGGMATICH i

1.

Name of facility:

Peach Bottom Unit 3 2.

Scheduled date for next refueling shutdowns March 7, 1981 3

Scheduled date for restart l'ollowing refueling:

August 1h, 1981 h.

Will reiteling or. resumption of operation thereafter require a technical specification changei or other license amendment?

Yes.

If answer is yise,' :<nat, in general, will these be?

Technical specification changes to acconnodate reload IVel.

Modifications to reactor core operating limits are expected.

5 Scheduled date(s) for submitting proposed licensing action and l

supporting information:

March 6, 1981 6.

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

new or fifferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

Ncne expected.

7.

Thenumberoffuelassemblies(a)inthecoreand(b)inthespent fuel storage Pools (a) Core - 76h Fuel Aseeablies (b) Fuel Pool - 712 Irradiated Fuel Assemblies 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has bee-1 requested l

or is planned, in number of fuel assemblies:

The spent fusi pool storage capacity has been relicensed for 2816 fuel assemblies.

l 9

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

l c

September, 1991 l

PE A C61 110TTor' AT0" f C POW 4 "TATim N ARRATIVE SUM"ARY nF OPEP ATI!!G EX PERTMICES JAMUARY 1991 a

UNIT 2 OPERATIONS A load reduction was taken at the beginning of the month to accommodate a control rod pattern adjustment.

On January 6, the unit was removed from service to accommodate repair of ar.

electro-hydraulic control system fluid leak.

During the outage tests were performed on the scram discharge volume monitoring sy: tem.

During the return to service on January 7, a bearing failed in the 2B recirculation pump hydraulic coupling control system.

On January 10, a load reduction was taken to accommodate' a control rod pattern adjustment.

On January 13, an orderly shutdown wss conducted until the E-3 diesel generator breaker could be replaced with a spare and successfully tested.

C, j

January 17, a load reduction was taken to accommodate a control rod pattern adjustment and unexpected repairs to the 2D main steam line radiation =onitor.

On January 20, a load drop was taken to accommodate a control rod adjustment.

On January 22, the unit was removed from service to accommodate repairs to d2 turbine control valve servo mechanism.

Additionaly load drops were taken to accommodate control rod pattern adjustments.

Significant safety related maintenance performed during the month was: RCIC flow transmitter for full scale failure, 2B recirculation pump MG set hudraulic coupling scoop tube control failure, E-3 diesel generator breaker failure to close, Group III isolation relay failure, and 2D main steam line radiation monitor up scale failure due to a grounded cable.

UNIT 1 OPERATION The Unit operated through the month at full power except for a brief load drop on January 10 to accommodate a control rod pattern adjustment and January 20, to accommodate repair of tube leaks in the A and B condensers.

n Significant sa'fety related maintenance performed during the month was: 3b core spray pump breaker for charging pump failure and l

HPCI outboard bearing leak.

l l

l I

m.~

.