ML20058L554: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
(One intermediate revision by the same user not shown)
Line 2: Line 2:
| number = ML20058L554
| number = ML20058L554
| issue date = 11/30/1993
| issue date = 11/30/1993
| title = Monthly Operating Repts for Nov 1993 for Limerick Generating Station.W/931213 Ltr
| title = Monthly Operating Repts for Nov 1993 for Limerick Generating Station
| author name = Mcmenamin J, Muntz J
| author name = Mcmenamin J, Muntz J
| author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
| author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:_     .. _                            ._ _        .                            _    _-
{{#Wiki_filter:_
l L                                                    -
l P11ILADELPHIA ELECTRIC COMPANY.
T.S.6.9.1.6.         l P11ILADELPHIA ELECTRIC COMPANY.                                        f LIMERICK GENERATING STATION                                       ,
T.S.6.9.1.6.
P. O. BOX 2300 SANATOGA, PA 19464-2300                                       f December.13, 1993           l Docket Nos. 50-352           !
l L
                                                                                    '50-353       'f
f LIMERICK GENERATING STATION P. O. BOX 2300 f
,                                                                  . License Nos. NPF-39           ,
SANATOGA, PA 19464-2300 December.13, 1993 l
                                                                                    'NPF-85       ij i
Docket Nos. 50-352
U. S. Nuclear Regulatory Commi'ssion                                                   l l            Attn:   Document Control Desk                                                         .
'50-353
!          Washington, DC 20555                                                                     .
'f
. License Nos. NPF-39
'NPF-85 ij i
U. S. Nuclear Regulatory Commi'ssion l
Attn:
Document Control Desk Washington, DC 20555


==Subject:==
==Subject:==
Limerick Generating Station Monthly Operating Report For .
Limerick Generating Station Monthly Operating Report For.
l                       Units 1 and 2                                                               ,
l Units 1 and 2 i
i Enclosed are the monthly. operating reports-for Limerick Units                   '
Enclosed are the monthly. operating reports-for Limerick Units 1 and 2 for the month of November, 1993 - forwarded pursuant _ to Technical Specification 6.9.1.6.
1 and 2 for the month of November, 1993 - forwarded pursuant _ to                       '
Technical Specification 6.9.1.6.
very truly yours,.
very truly yours,.
2P5L 'N J   es A. Muntz       .    .                    !
2P5L 'N J
Director - Site Engineering jjm Enclosures cc:   T.-T. Martin, Administrator,-Region I, USNRC~(w/ enclosures)
es A. Muntz Director - Site Engineering jjm Enclosures cc:
T.-T. Martin, Administrator,-Region I, USNRC~(w/ enclosures)
N. S. Perry, USNRC Senior Resident-Inspector LGS ~
N. S. Perry, USNRC Senior Resident-Inspector LGS ~
(w/ enclosures)                                                                   .
(w/ enclosures)
D. R. Helwig, Vice President, Limerick Generating Station                         I i
D. R. Helwig, Vice President, Limerick Generating Station i
170fm                                                                                 u 93                                                                                        ,
170fm u
gDg217007493121g2 ADOCK0500g            .-
gDg217007493121g2
                                                                                        .gKy         j 11     \
.gKy j
93 ADOCK0500g 11
\\


    .      .                                                Dock %t No. 50-352 :
Dock %t No. 50-352 Attcchm:nt to Monthly Operating Report for November 1993 Limerick Generating Station Unit 1 November 1 through November 30, 1993 I.
Attcchm:nt to Monthly !
Narrative Summary of Operatine Exoeriences Unit 1 began this operating period at 99% of rated thermal power (RTP).
Operating Report for November 1993 Limerick Generating Station Unit 1 November 1 through November 30, 1993 I. Narrative Summary of Operatine Exoeriences Unit 1 began this operating period at 99% of rated thermal power (RTP).
On November 5, 1993 at 1200 hours power was reduced to 95%
On November 5, 1993 at 1200 hours power was reduced to 95%
RTP in order to remove extraction steam to the 5th feedwater heaters. Power was restored to 100% RTP at 1345 hours.
RTP in order to remove extraction steam to the 5th feedwater heaters.
Power was restored to 100% RTP at 1345 hours.
On November 12, 1993 power began to decrease due to end-of-cycle coastdown.
On November 12, 1993 power began to decrease due to end-of-cycle coastdown.
On November 14, 1993 at 1000 hours power was reduced to 96%
On November 14, 1993 at 1000 hours power was reduced to 96%
RTP for main turbine valve testing. Power was restored to 98.5% RTP shortly thereafte-                                     .
RTP for main turbine valve testing.
On November 28, 1993 at 0525 hours power was reduced to 88.5% RTP due to high turbine backpressure. Power was             i restored to 92% RTP by 0855 hours.
Power was restored to 98.5% RTP shortly thereafte-On November 28, 1993 at 0525 hours power was reduced to 88.5% RTP due to high turbine backpressure.
Power was i
restored to 92% RTP by 0855 hours.
On November 28, 1993 at 2100 hours power was reduced to 50%
On November 28, 1993 at 2100 hours power was reduced to 50%
RTP for performance of control rod hydraulic control unit work and condenser cleaning.
RTP for performance of control rod hydraulic control unit work and condenser cleaning.
Unit 1 ended this operating period at 50% of rated thermal power with control rod maintenance work continuing.               1 II. Challences to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief         ,
Unit 1 ended this operating period at 50% of rated thermal power with control rod maintenance work continuing.
Valves during the month of November.                             i i
II.
Challences to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of November.
i i


QVERAGE DQILY UNIT POWER LEVEL
QVERAGE DQILY UNIT POWER LEVEL DOC'tET NO. 50 - 352 UNIT LIMERICK UNIT 1 DATE DECEMBER 9, 1993 COMPANY PHILADELPHIA ELECTRIC COMPANY JOHN J.
* DOC'tET NO. 50 - 352                                                                                                                   .
MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 MONTH NOVEMBER 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
UNIT LIMERICK                     UNIT 1 DATE DECEMBER 9,                 1993                                                                                           ,
-(MWE-NET)
COMPANY PHILADELPHIA ELECTRIC COMPANY JOHN J. MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 MONTH NOVEMBER 1993 DAY                       AVERAGE DAILY POWER LEVEL             DAY         AVERAGE DAILY POWER LEVEL
(MWE-NET) 1 1026 17 986 2
                                                                                                                            -(MWE-NET)                                               (MWE-NET) 1                             1026                       17                           986 2                               1024                       10                           987 3                               1017                       19                           975 4                               1015                       20                           978 5                               1006                   '. 21                           975 6                               1018                       22                           969 7                               1020                       23                           968 8                               1021                     24                             957 9                               1021                     25                             959 10                               1021                     26                             952 11                               1022                     27                             942 12                               1007                     28                             869                                                     e 13                               1008                     29                           '430 14                               992                     30-                           445 15                               987 16                               993
1024 10 987 3
__ _ _ _ _ . _ . . _ _ . _ _ _ _ _ . _ _ . . _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ ._ _ _                                , ..              . . . . . '._... - ,, . . _ . . . . _ . . _ _. . . . _ _ . . _ . _ , _ . .  . .__, a _ u . . . . . . -
1017 19 975 4
1015 20 978 5
1006
'. 21 975 6
1018 22 969 7
1020 23 968 8
1021 24 957 9
1021 25 959 10 1021 26 952 11 1022 27 942 12 1007 28 869 e
13 1008 29
'430 14 992 30-445 15 987 16 993
..__, a _ u...... -


OPEROTING DATA REPORT                                                                                                                                                                                                                                     ,
OPEROTING DATA REPORT DOCGET NO. 50 - 352 DATE DECEMBER 9 1993 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY
DOCGET NO. 50 - 352                                                                                                                                                                     ,
--...-----....._- _=--....-.
DATE DECEMBER 9 1993 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY                                                                                                                                                   '
JOHN J. MCMENAMIN 4
                                                                                                                                                                                                                                                --...-----....._- _=--....-.
REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 OPERATING STATUS
JOHN J. MCMENAMIN                                                                                                                                                   4 REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION --3794                                             -
~~h0TES: THERE WAS ONE LOAb DROP
OPERATING STATUS
: 1. UNIT UAME: LIMEftICK UNIT 1 2.
: 1. UNIT UAME: LIMEftICK -..----------          UNIT 1                                                      ~~h0TES: THERE WAS ONE LOAb DROP
REPORTING PERIOD:
: 2. REPORTING PERIOD:           NOVEMBER. 1993                                                                                             GREATER THAN 20% THIS MONTH-                                                                                                                                             ,
NOVEMBER. 1993 GREATER THAN 20% THIS MONTH-3.
: 3. LICENSED THERMAL POWER (MWT):                                               3293                                                       TO PERFORM CONTROL ROD'
LICENSED THERMAL POWER (MWT):
: 4. NAMEPLATE RATING (GROSS MWE):                                                 1138                                                     HYDRAULIC CONTROL UNIT' WORK
3293 TO PERFORM CONTROL ROD' 4.
: 5. DESIGN ELECTRICAL RATING (NET MWE):                                           1055                                                     AND CONDENSER CLEANING.
NAMEPLATE RATING (GROSS MWE):
                                                                                            'G.       MAXIMUM DEPENDADLE CAPACITY (GROSS WWE): 1092                                                                                                                                                                                                                                                                   1
1138 HYDRAULIC CONTROL UNIT' WORK
: 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):.                                       1055
: 5. DESIGN ELECTRICAL RATING (NET MWE):
                                                                                                                                                                                                                                                                                                        = . -
1055 AND CONDENSER CLEANING.
'G. MAXIMUM DEPENDADLE CAPACITY (GROSS WWE): 1092 1
7.
MAXIMUM DEPENDABLE CAPACITY (NET MWE):.
1055
=. -
: 8. - IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER'3 THROUGH_7) SINCE LAST REPORT. GIVE REASONS:
: 8. - IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER'3 THROUGH_7) SINCE LAST REPORT. GIVE REASONS:
i
i
: 9. POWER LEVEL'TO WHICH RESTRICTED. IF ANY (N'ET MWE):
: 9. POWER LEVEL'TO WHICH RESTRICTED. IF ANY (N'ET MWE):
: 10. REASONS FOR RESTRICTIONS. IF ANY:
: 10. REASONS FOR RESTRICTIONS. IF ANY:
THIS MONTH                                 YR-TO-DATE.                                   ' CUMULATIVE
THIS MONTH YR-TO-DATE.
: 11. HOURS IN REPORTING PERIOO -                                                                                                 ' 720                                     8.016                                           68.640                                                                                         -
' CUMULATIVE
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL                                                                                   720.0                                   7.905.9g                                 '55.455.1
: 11. HOURS IN REPORTING PERIOO -
                                                                                      - 13. REACTOR RESERVE. SHUTDOWN HOURS                                                                                                   0.0                                           0.0                                               0.0
' 720 8.016 68.640
                                                                                                                                                                                            -                _-                -=                                                           .
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 7.905.9g
14 HOURS GENERATOR ON-LINE                                                                                            c720.0                                     -7.882.6; 54.440.8-
'55.455.1
                                                                                    - 15. UNIT RESERVE SHUTDOWN HOURS                                                                                                       0.0 -                                         0.0                                             .O.0
- 13. REACTOR RESERVE. SHUTDOWN HOURS 0.0 0.0 0.0
                                                                                                                                                                                                          =........
-=
                                                                                                                                                                                                                                                                                                =- - --
c720.0
                                                                                      - 16. GROS $ THERMAL ENERGY GENERATED (MWH)                                                                       . 2.224.078.                               25.649,2487                                 - 167.382.713.                 .. -
-7.882.6; 54.440.8-14 HOURS GENERATOR ON-LINE
17.' GROSS ELECTRICAL ENERGY GENERATED (MWH)-                                                 .
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 -
                                                                                                                                                                                                            '711.700'                         ._
0.0
                                                                                                                                                                                                                                                      .. 8.409.020.
.O.0
=........
=- - --
- 16. GROS $ THERMAL ENERGY GENERATED (MWH)
. 2.224.078.
25.649,2487
- 167.382.713.
17.' GROSS ELECTRICAL ENERGY GENERATED (MWH)-
'711.700'
.. 8.409.020.
54.385.160
54.385.160
: 18. NET ELECTRICAL' ENERGY' GENERATED (MWH).                                                                     . 686.146                                   8.'113.960)                                 - 52.154.477.'     --- .-
: 18. NET ELECTRICAL' ENERGY' GENERATED (MWH).
                                                                                                                                                                                            -          .....-s-..                              ----.-------                                    ...
. 686.146 8.'113.960)
PAGE'1 OF 2                                                                                                   +
- 52.154.477.'
                                                                                                                                                                                                                                                                                                                                                                                                                      +
.....-s-..
PAGE'1 OF 2
+
+
t.
t.
i t
i t
e_.u -am_u__                                            -mm_._.i_--.cs.-___m_.__.____.___                  m_2._me+       -a_    -*---+a..a__          + w oree w es 'ea=r.-e 4 m '-             vnwtw       --st--- -t   *'-,++wwe~T-e           rF -A-? e e .wm-'se   ve in Nw
T e.u
* v ervreeMed         weeis- e   ,4     wmab erad hr wre i s --w-e- 4 Tew W2e.-._m.u*-- .er.w.m u.u-.---_ia..--       -_.a_
-am u
-mm..i --.cs.-
m.
m 2. me+
-a
-*---+a..a
+ w oree w es
'ea=r.-e 4 m '-
vnwtw
--st---
-t
*'-,++wwe~T-e rF -A-? e e
.wm-'se ve in Nw
* v ervreeMed weeis-e
,4 wmab erad hr wre i s
--w-e-4 ew W2e.-. m.u*--
.er.w.m u.u-.--- ia..--
-.a


OPERQTING DGTo REPORT (CONTINUED)                                                     DOCKET NO. 50 - 352                                                 ,
OPERQTING DGTo REPORT (CONTINUED)
_ _ _ . = .
DOCKET NO. 50 - 352
DATE DECEMBER 9,           1993 THIS MONTH             VR-TO-DATE                       CUMULATIVE                                                                 .
_ _ _. =.
: 19. UNIT SERVICE FACTOR                                                                                         100.0                   98.3                                   79.3
DATE DECEMBER 9, 1993 THIS MONTH VR-TO-DATE CUMULATIVE
: 20. UNIT AVAILABILITY FACTOR                                                                                     100.0                   98.3                                   79.3
: 19. UNIT SERVICE FACTOR 100.0 98.3 79.3
: 21. UNIT CAPACITY FACTOR (USING MOC NET)                                                                           90.3                   95.9                                   72.0
: 20. UNIT AVAILABILITY FACTOR 100.0 98.3 79.3
: 22. UNIT CAPACITY FACTOR (USING DER NET)                                                                           90.3                   95.9                                   72.0
: 21. UNIT CAPACITY FACTOR (USING MOC NET) 90.3 95.9 72.0
: 23. UNIT FORCED OUTAGE RATE                                                                                         0.0                     1.7                                   4.8
: 22. UNIT CAPACITY FACTOR (USING DER NET) 90.3 95.9 72.0
: 23. UNIT FORCED OUTAGE RATE 0.0 1.7 4.8
: 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):
: 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):
STH REFUELING OUTAGE: 1/79/94: 45 DAYS
STH REFUELING OUTAGE: 1/79/94: 45 DAYS
: 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
: 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
26.. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):                                                                     FORECAST             ACHIEVED INITIAL CRITICALITY                                     12/19/84         12/22/84 INITIAL ELECTRICITY                             MID APRIL 85             4/13/85 COMMERCIAL OPERATION                               IST QTR 86             2/01/86 PAGE 2 0F 2.
26.. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):
_. _ . . _ . _ _ _ . _ _ _ _ . _                                                    __            _ _ _ .__ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                              .              . _                  -        . . . , _ , .                .      . _ _ . _ . . , _ . ...._s __._. . _ _ _ _ _ . ,
FORECAST ACHIEVED INITIAL CRITICALITY 12/19/84 12/22/84 INITIAL ELECTRICITY MID APRIL 85 4/13/85 COMMERCIAL OPERATION IST QTR 86 2/01/86 PAGE 2 0F 2.
.... s


G UNIT SHUTDOWNS AND POWER REDUCTIONS                                                           ' DOCKET NO. 50 - 352 UNIT NAKE LIKERICK                                     UNIT 1
G UNIT SHUTDOWNS AND POWER REDUCTIONS
                                                                                                                                                                                                                                                                                                            ^
' DOCKET NO. 50 - 352 UNIT NAKE LIKERICK UNIT 1 DATE DECEMBER 9 1993
DATE DECEMBER 9 1993
^
* REPORT MONTH NOVEMBER. 1993                                                           COMPLETED BV PHILADELPHIA ELECTRIC COMPANY JOHN J. MCMENAMIN                                                                                                         ,
REPORT MONTH NOVEMBER. 1993 COMPLETED BV PHILADELPHIA ELECTRIC COMPANY JOHN J. MCMENAMIN REPORTS ENGINEER SITE ENGINEERING n
REPORTS ENGINEER                                                                                                             '
LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3T94
SITE ENGINEERING                                                                                                                         n LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3T94
- - - - - - - - - _ _ - - - - - -...... _ - - - - - _.. _ _ - - - - -..... = = - - - - - - = - - -
                                    - - - - - - - - - _ _ - - - - - - . . . . . . _ - - - - - _ . . _ _ - - - - - . . . . . = = - - - - - - = - - -          . . . - -            ..                                    -----                -- - - - - - - - - - -
METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND' CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.
METHOD OF                     LICENSEE         SYSTEM COMPONENT                   CAUSE AND' CORRECTIVE TYPE DURATION REASON SHUTTING DOWN                                           EVENT         CODE               CODE               ACTION TO NO.         DATE   (1)     (HOURS)             (2)       REACTOR (3)                     REPORT *             (4)-             (5)           PREVENT RECURRENCE-26         931105   5     000.0                 H                   4                             N/A           CH             HTEXCH           REACTOR POWER WAS REDUCED TO 95% TO REMOVED THE STH FEEOWATER HEATER FROM SERVICE DUE TO COASTDOWN.                                                                                                                                   ;
DATE (1)
27       931114     S     000.0                 B                   4                             N/A           HA             INSTRU           REACTOR POWER WAS REDUCED TO 96% FOR                                                                                                                         '
(HOURS)
MAIN TURBINE VALVE TESTING.
(2)
28       931128     F     000.0                 d                   4                             N/A           HA             TURBIN           REACTOR POWER WAS REDUCED TO 88.5% TO REDUCE HIGH TURBINE BACKPRESSURE.
REACTOR (3)
29       931128     S     000.0                 8                   4                             N/A           RB             CONROD           REACTOR POWER WAS REDUCED TO 50% TO-PERFORM CONTROL ROD HYDRAULIC CONTROL.
REPORT *
UNIT MAINTENANCE AND TO PERFORM' CONDENSER CLEANING.                                                                                                                                         ,
(4)-
                                                                                                                                                                                                                                                                                                                    .I (1)                             (2)'                                                                                   '(3)'                                                 (4)
(5)
F - FORCED             REASON                                                                                   METHOD                                           EXHIBIT G ~ INSTRUCTIONS S - SCHEDULED           A- EQUIPMENT FAILURE (EXPLAIN)                                                         '1 - MANUAL                                     .FOR PREPARATION OF DATA B - MAINTENANCE _OR TEST                                                                 2 - MANUAL SCRAM.                                 ENTRY SHEETS FOR LICENSEE C - REFUELING                                                                           3 - AUTOMATIC SCRAM.                             EVENT REPORT (LER)
PREVENT RECURRENCE-26 931105 5
D - REGULATORY RESTRICTION                                                             OTHER (EXPLAIN)           '
000.0 H
                                                                                                                                                                              ' FILE.(NUREG-0161)
4 N/A CH HTEXCH REACTOR POWER WAS REDUCED TO 95% TO REMOVED THE STH FEEOWATER HEATER FROM SERVICE DUE TO COASTDOWN.
E - OPERATOR TRAINING +' LICENSE EXAMINATION F - ADMINISTRATIVE                                                                                                                                              -(5):'
27 931114 S
* G - OPERATIONAL ERROR ~ (EXPLAIN).
000.0 B
H - OTHER(EXPLAIN)                                                                                                                         EXHIBIT I - SAME SOURCE -                                                                                                                 t
4 N/A HA INSTRU REACTOR POWER WAS REDUCED TO 96% FOR MAIN TURBINE VALVE TESTING.
'( .
28 931128 F
000.0 d
4 N/A HA TURBIN REACTOR POWER WAS REDUCED TO 88.5% TO REDUCE HIGH TURBINE BACKPRESSURE.
29 931128 S
000.0 8
4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 50% TO-PERFORM CONTROL ROD HYDRAULIC CONTROL.
UNIT MAINTENANCE AND TO PERFORM' CONDENSER CLEANING.
i
. I (1)
(2)'
'(3)'
(4)
F - FORCED REASON METHOD EXHIBIT G ~ INSTRUCTIONS S - SCHEDULED A-EQUIPMENT FAILURE (EXPLAIN)
'1 - MANUAL
.FOR PREPARATION OF DATA B - MAINTENANCE _OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER)
D - REGULATORY RESTRICTION OTHER (EXPLAIN)
' FILE.(NUREG-0161)
E - OPERATOR TRAINING +' LICENSE EXAMINATION H - OTHER(EXPLAIN)
~ (EXPLAIN).
-(5):'
F - ADMINISTRATIVE G - OPERATIONAL ERROR EXHIBIT I - SAME SOURCE -
t
'(
4
4
                                                    -                    .  ,.s ..-',...I.       ,-,.-,*.~-#.-.4-      , , - e.,t.e.     .  ,m...   ~,Es -c.,-.As   .e e -   ...e.,,+-d.-               ,.).*%e,           er ,v % ,..a               webi.               ,-. . , . .. , _ + , . ,
,.s..-',...I.
,-,.-,*.~-#.-.4-e.,t.e.
,m...
~,Es
-c.,-.As
.e e -
...e.,,+-d.-
,.).*%e, er,v %
,..a webi.
,-..,..., _ +,.,


l 1
l 1
        -      .                                                        Dockst No. 50-353   .)
Dockst No. 50-353
                                                                    ~Attachm:nt to Monthly.. _j Operating Report for.
.)
                                                                            ' November'1993 Limerick Generating Station Unit 2 November 1 through November 30,'1993 i
~Attachm:nt to Monthly..
I.         Narrative Summary of Operatina Experiences Unit 2 began this operating period at 100% of ratedLthermal               ;
_j Operating Report for.
power (RTP) .                                                             j On November 6,     1993 at 0823 hours power was reduced to 80%~         l RTP for a control rod pattern adjustment and-SCRAM time testing. Power was. restored to 100% RTP at 2120 hours.               !
' November'1993 Limerick Generating Station Unit 2 November 1 through November 30,'1993 i
I.
Narrative Summary of Operatina Experiences Unit 2 began this operating period at 100% of ratedLthermal power (RTP).
j On November 6, 1993 at 0823 hours power was reduced to 80%~
l RTP for a control rod pattern adjustment and-SCRAM time testing.
Power was. restored to 100% RTP at 2120 hours.
On November 14, 1993 at 1320 hours power was reduced to 97%
On November 14, 1993 at 1320 hours power was reduced to 97%
RTP for a centrol rod exercise test and then restored to                   ,
RTP for a centrol rod exercise test and then restored to 100% RTP shortly thereafter.
100% RTP shortly thereafter.
On November 21, 1993 at 0934 hours power.was reduced to 92%~
On November 21, 1993 at 0934 hours power.was reduced to 92%~
RTP for Main Turbine Valve Testing.         Power-was restored to J
Power-was restored to RTP for Main Turbine Valve Testing.
100% RTP at 1250 hours.                                                 l Unit 2 ended this' operating period at'100%-of ratedLthermal-           ;
J 100% RTP at 1250 hours.
power.
l Unit 2 ended this' operating period at'100%-of ratedLthermal-power.
II.       Challences to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief                   l l
II.
Valves during the month of November.                                     :
Challences to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief l
Valves during the month of November.
i l
i l
l 1.
l 1.
Line 162: Line 256:
I
I


DVERAGE DQILV UNIT POWER LEVEL                                                                                                                                                                   ,
DVERAGE DQILV UNIT POWER LEVEL DOCKET NO. 50 - 353 UNIT LIMERICK UNIT 2 DATE DECEvBER 9, 1993 COMPANY PHILADELPHIA ELECTRIC COMPANY JOHN J.
DOCKET NO. 50 - 353                                                                                                                                                       .
MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 MONTH NOVEMBER 1993 DAY AVERAGE DAILY POWER LEVEL DAV AVERAGE DAILY POWER LEVEL (MWE-NET)
UNIT LIMERICK                             UNIT 2 DATE DECEvBER 9,                       1993                                                                                                                 ,
(MWE-NET) 1 1070 17 1065 2
COMPANY PHILADELPHIA ELECTRIC COMPANY JOHN J. MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 MONTH NOVEMBER 1993 DAY   AVERAGE DAILY POWER LEVEL                             DAV       AVERAGE DAILY POWER LEVEL (MWE-NET)                                                                   (MWE-NET) 1                   1070                                   17                                         1065 2                   1071                                   18                                         1070 3                   1070                                   19                                         1063 4                   1072                                   20                                           1071 5                   1064                                   21                                           1060 6                     990                                 22                                           1071
1071 18 1070 3
: 7.                   1073                                   23                                         1075 8                   1073                                   24                                         1065 9                   1073                                   25                                         1075 10                   1072                                   26                                         1074 11                   1071                                   27                                         1065.
1070 19 1063 4
12'                   1068                                   28                                         1062 13                   1069                                   29                                         1067 14                   1060                                   30                                         1071 15                   1056 16                   1066
1072 20 1071 5
_ . ,                          ,                        .    . - . . , . . . . _ . . . .          -        . , . . . . - _ , . . - - - .-_ .. .      .. _ . _ . - - - _ . - . . - - . . . _ _ . - . .. _ , ~ ~ . . _ - . . . . - . - - , _ . - - -
1064 21 1060 6
990 22 1071 7.
1073 23 1075 8
1073 24 1065 9
1073 25 1075 10 1072 26 1074 11 1071 27 1065.
12' 1068 28 1062 13 1069 29 1067 14 1060 30 1071 15 1056 16 1066
_, ~ ~.. _ -.... -. - -, _. - - -


OPERATING DATA REPORT                                                                                                                                                               ,
OPERATING DATA REPORT DOCGET NO. 50 - 353 DATE DECEMBER 9.
DOCGET NO. 50 - 353                                                                                                           .
1993 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY JOHN J.
DATE DECEMBER 9. 1993 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY                                                                                         ,
MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 OPERATING STATUS 1.
JOHN J. MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 OPERATING STATUS                                                                                                               _ _ _ - _ _ _ _ _ - - - - _ _ . . . - - . - . . _ - - - -                          ----_
UNIT NAME: LIMERICK UNIT 2 NOTES: THERE WAS ONE LOAD DROP 2.
: 1. UNIT NAME: LIMERICK                                                                     UNIT 2                                               NOTES: THERE WAS ONE LOAD DROP
REPORTING PERIOD:
: 2.               REPORTING PERIOD:                                           NOVEMBER, 1993                                                                       GREATER THAN 20% THIS
NOVEMBER, 1993 GREATER THAN 20% THIS 3.
: 3.               LICENSED THERMAL POWER (MWT):                                                                                   3293                             MONTH TO PERFORM CONTROL
LICENSED THERMAL POWER (MWT):
: 4.               NAMEPLATE RATING (GROSS MWE):                                                                                     1138                           ROD PATTERN ADJUSTMENTS
3293 MONTH TO PERFORM CONTROL 4.
: 5.               DESIGN ELECTRICAL RATING (NET MwE):                                                                               1055                           AND SCRAM TIME TESTING.
NAMEPLATE RATING (GROSS MWE):
6.
1138 ROD PATTERN ADJUSTMENTS 5.
MAXIMUM DEPENOABLE CAPACITY (GROSS MWE): 10 ]
DESIGN ELECTRICAL RATING (NET MwE):
7 MAXIMUM DEPENDABLE CAPACITY (NET WWE):                                                                                           1055
1055 AND SCRAM TIME TESTING.
: 8.               IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
: 6. MAXIMUM DEPENOABLE CAPACITY (GROSS MWE): 10 ]
: 9.               POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
7 MAXIMUM DEPENDABLE CAPACITY (NET WWE):
1055 8.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
9.
POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
: 10. REASONS FOR RESTRICTIONS, IF ANY:
: 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH                       YR-TO-DATE                           CUMULATIVE
THIS MONTH YR-TO-DATE CUMULATIVE
: 11. HOURS IN REPORTING PERIOD                                                                                                                                   720                               8,016                             34.152
: 11. HOURS IN REPORTING PERIOD 720 8,016 34.152
_~_--___.___                       -.....-... .                          =             __.--.
_~_--___.___
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL                                                                                                                   720.0                           6.657.8                           29,898'6       .
=
_--____...--                      ... -___..._                          -              _=___.
: 12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 6.657.8 29,898'6
: 13. REACTOR RESERVE SHUTDOWN HOURS                                                                                                                               0.0                                   0.0                                 0.0
_=___.
: 14. HOURS GENERATOR ON-LINE                                                                                                                                 720.0                           6,546.2                           29,202.7
: 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
: 15. UNIT RESERVE SHUTDOWN HOURS                                                                                                                                 0.0                                   0.0                                 0.0
: 14. HOURS GENERATOR ON-LINE 720.0 6,546.2 29,202.7
: 16. GROSS THERMAL ENERGY GENERATED (MWH)                                                                                                           2,358,192                       20,890.734                           92.856,884
: 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
: 17. GROSS ELECTRICAL ENERGY GENERATED (MWH)                                                                                                             792,530                     .6,916.340                           30,669,446
: 16. GROSS THERMAL ENERGY GENERATED (MWH) 2,358,192 20,890.734 92.856,884
: 18. NET ELECTRICAL ENERGY GENERATED (MWH)                                                                                                                 767.261                     6,670,604                           29,533.651 PAGE 1 OF 2
: 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 792,530
.6,916.340 30,669,446
: 18. NET ELECTRICAL ENERGY GENERATED (MWH) 767.261 6,670,604 29,533.651 PAGE 1 OF 2


O OPERQTING DQTA REPORT (CONTINUED)                                                               DOCKEY NO. 50 - 353                                               .
O OPERQTING DQTA REPORT (CONTINUED)
__..____ ._________ ______...                                                                          ~*
DOCKEY NO. 50 - 353
DATE DECEMBER 9,             1993 THIS MONTH                         YR-TO-DATE                       CUMULATIVE                                                   ,
~*
: 19. UNIT SERVICE FACTOR                                                                     100.0                               81.7                               85.5
DATE DECEMBER 9, 1993 THIS MONTH YR-TO-DATE CUMULATIVE
: 20. UNIT AVAILABILITY FACTOR                                                                 100.0                               81.7                               85.5
: 19. UNIT SERVICE FACTOR 100.0 81.7 85.5
: 21. UNIT CAPACITY FACTOR (USING MDC NET)                                                     101.0                               78.9                               82.0
: 20. UNIT AVAILABILITY FACTOR 100.0 81.7 85.5
: 22. UNIT CAPACITY FACTOR (USING DER NET)                                                     101.0                               78.9                               82.0
: 21. UNIT CAPACITY FACTOR (USING MDC NET) 101.0 78.9 82.0
: 23. UNIT FORCED OUTAGE RATE                                                                       O.0                             2.7                                     4.2
: 22. UNIT CAPACITY FACTOR (USING DER NET) 101.0 78.9 82.0
                                                                                                                                      - _ = _ _ - = - _ - _ - _ _ _       __.__....___
: 23. UNIT FORCED OUTAGE RATE O.0 2.7 4.2
- _ = _ _ - = - _ - _ - _ _ _
: 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):
: 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):
: 25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUPa
: 25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUPa
: 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):                                                       FORECAST                 ACHIEVED INITIAL CRITICALITY                                                   08/12/89           08/12/89 INITIAL ELECTRICITY                                                   09/01/89-           09/01/89 COMMERCIAL OPERATIO.4                                                 02/01/90' 01/08/90 PAGE 2 OF 2
: 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):
  .__ . _ . _ . _ . _ _ _ - - _ _ _ - - _ - - _ _ _ _ _ _ .                - _ _ - _ _ _ - - - _ - _ _ _ _              - - .__    ,      - -              -. . , . .                    ---                          , . . . ~             , ~ . - . . - .~ .- . - . - - . .     - ._
FORECAST ACHIEVED INITIAL CRITICALITY 08/12/89 08/12/89 INITIAL ELECTRICITY 09/01/89-09/01/89 COMMERCIAL OPERATIO.4 02/01/90' 01/08/90 PAGE 2 OF 2
,... ~
~
.~.-. -. - -..


UNIT SHUTDOWN 5 AND POWER REDUCTIONS                                 DOCKET NO. 50 - 353                                                   ,
UNIT SHUTDOWN 5 AND POWER REDUCTIONS DOCKET NO. 50 - 353 UNIT NA%E LI~ERICK UNIT 2 REPORT MONTH NOVEMBER, 1993 COMPLETED BY PHILAOELPHIA ELECTRIC COMPANY JOHN J. MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 32T-1200 EXTENSION 3T94 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOwN EVENT CODE CODE ACTION TO NO.
UNIT NA%E LI~ERICK                   UNIT 2 REPORT MONTH NOVEMBER, 1993                                 COMPLETED BY PHILAOELPHIA ELECTRIC COMPANY                           .
DATE (1)
JOHN J. MCMENAMIN                               ",
(HOURS)
REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 32T-1200 EXTENSION 3T94 METHOD OF             LICENSEE           SYSTEM COMPONENT   CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOwN                             EVENT           CODE     CODE       ACTION TO NO. DATE             (1) (HOURS)                 (2)     REACTOR (3)           REPORT s             (4)       (5)   PREVENT RECURRENCE 43   931106             S   000.0                   0         4                     N/A             RB     CONROD     REACTOR POWER WAS REDUCED TO 80% FOR CONTROL RCD PATTERN ADJUSTMENTS AND TO PERFORM SCRAM TIME TESTING.
(2)
44   931114             S   000.0                   B         4                     N/A             RB     CONROD     REACTOR POWER WAS REDUCED TO 9T% FOR CONTROL ROD EXERCISE TESTING.
REACTOR (3)
45   931121             $    000.0                   B         4                     N/A             HA     INSTRU     REACTOR POWER WAS REDUCED TO 92% FOR MAIN TURBINE VALVE TESTING.
REPORT s (4)
(1)                                     (2)                                                                 (3)                             (4)
(5)
F - FORCED                 REASON                                                                       METHOD                       EXHIBIT G - INSTRUCTIONS S - SCHEDULED               A - EQUIPMENT FAILURE (EXPLAIN)                                               1 - MANUAL                   FOR PREPARATION OF DATA B - MAINTENANCE OR-TEST                                                       2 - MANUAL SCRAM.           ENTRY SHEETS FOR LICENSEE C - REFUELING                                                                 3 - AUTOMATIC SCRAM.     ' EVENT REPORT (LER)
PREVENT RECURRENCE 43 931106 S
D - REGULATCRV RESTRICTION -                                                 4 - OTHER (EXPLAIN)             FILE (NUREG-0161)
000.0 0
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE                                 .'                                                                  (5)
4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 80% FOR CONTROL RCD PATTERN ADJUSTMENTS AND TO PERFORM SCRAM TIME TESTING.
44 931114 S
000.0 B
4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 9T% FOR CONTROL ROD EXERCISE TESTING.
45 931121 000.0 B
4 N/A HA INSTRU REACTOR POWER WAS REDUCED TO 92% FOR MAIN TURBINE VALVE TESTING.
(1)
(2)
(3)
(4)
F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR-TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
' EVENT REPORT (LER)
D - REGULATCRV RESTRICTION -
4 - OTHER (EXPLAIN)
FILE (NUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER(EXPLAIN)                                                                                         EXHIBIT I - SAME SOURCE
H - OTHER(EXPLAIN)
.-                  __ _ _                        - _ - - - _ _ _              - __--__- ___-_- - - -                                  . . . . _                              .                            . - . , - . .  - -}}
EXHIBIT I - SAME SOURCE
- -}}

Latest revision as of 08:16, 17 December 2024

Monthly Operating Repts for Nov 1993 for Limerick Generating Station
ML20058L554
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 11/30/1993
From: Mcmenamin J, Muntz J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9312170074
Download: ML20058L554 (10)


Text

_

l P11ILADELPHIA ELECTRIC COMPANY.

T.S.6.9.1.6.

l L

f LIMERICK GENERATING STATION P. O. BOX 2300 f

SANATOGA, PA 19464-2300 December.13, 1993 l

Docket Nos. 50-352

'50-353

'f

. License Nos. NPF-39

'NPF-85 ij i

U. S. Nuclear Regulatory Commi'ssion l

Attn:

Document Control Desk Washington, DC 20555

Subject:

Limerick Generating Station Monthly Operating Report For.

l Units 1 and 2 i

Enclosed are the monthly. operating reports-for Limerick Units 1 and 2 for the month of November, 1993 - forwarded pursuant _ to Technical Specification 6.9.1.6.

very truly yours,.

2P5L 'N J

es A. Muntz Director - Site Engineering jjm Enclosures cc:

T.-T. Martin, Administrator,-Region I, USNRC~(w/ enclosures)

N. S. Perry, USNRC Senior Resident-Inspector LGS ~

(w/ enclosures)

D. R. Helwig, Vice President, Limerick Generating Station i

170fm u

gDg217007493121g2

.gKy j

93 ADOCK0500g 11

\\

Dock %t No. 50-352 Attcchm:nt to Monthly Operating Report for November 1993 Limerick Generating Station Unit 1 November 1 through November 30, 1993 I.

Narrative Summary of Operatine Exoeriences Unit 1 began this operating period at 99% of rated thermal power (RTP).

On November 5, 1993 at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> power was reduced to 95%

RTP in order to remove extraction steam to the 5th feedwater heaters.

Power was restored to 100% RTP at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />.

On November 12, 1993 power began to decrease due to end-of-cycle coastdown.

On November 14, 1993 at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> power was reduced to 96%

RTP for main turbine valve testing.

Power was restored to 98.5% RTP shortly thereafte-On November 28, 1993 at 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br /> power was reduced to 88.5% RTP due to high turbine backpressure.

Power was i

restored to 92% RTP by 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br />.

On November 28, 1993 at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> power was reduced to 50%

RTP for performance of control rod hydraulic control unit work and condenser cleaning.

Unit 1 ended this operating period at 50% of rated thermal power with control rod maintenance work continuing.

II.

Challences to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of November.

i i

QVERAGE DQILY UNIT POWER LEVEL DOC'tET NO. 50 - 352 UNIT LIMERICK UNIT 1 DATE DECEMBER 9, 1993 COMPANY PHILADELPHIA ELECTRIC COMPANY JOHN J.

MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 MONTH NOVEMBER 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

-(MWE-NET)

(MWE-NET) 1 1026 17 986 2

1024 10 987 3

1017 19 975 4

1015 20 978 5

1006

'. 21 975 6

1018 22 969 7

1020 23 968 8

1021 24 957 9

1021 25 959 10 1021 26 952 11 1022 27 942 12 1007 28 869 e

13 1008 29

'430 14 992 30-445 15 987 16 993

..__, a _ u...... -

OPEROTING DATA REPORT DOCGET NO. 50 - 352 DATE DECEMBER 9 1993 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY

--...-----....._- _=--....-.

JOHN J. MCMENAMIN 4

REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 OPERATING STATUS

~~h0TES: THERE WAS ONE LOAb DROP

1. UNIT UAME: LIMEftICK UNIT 1 2.

REPORTING PERIOD:

NOVEMBER. 1993 GREATER THAN 20% THIS MONTH-3.

LICENSED THERMAL POWER (MWT):

3293 TO PERFORM CONTROL ROD' 4.

NAMEPLATE RATING (GROSS MWE):

1138 HYDRAULIC CONTROL UNIT' WORK

5. DESIGN ELECTRICAL RATING (NET MWE):

1055 AND CONDENSER CLEANING.

'G. MAXIMUM DEPENDADLE CAPACITY (GROSS WWE): 1092 1

7.

MAXIMUM DEPENDABLE CAPACITY (NET MWE):.

1055

=. -

8. - IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER'3 THROUGH_7) SINCE LAST REPORT. GIVE REASONS:

i

9. POWER LEVEL'TO WHICH RESTRICTED. IF ANY (N'ET MWE):
10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH YR-TO-DATE.

' CUMULATIVE

11. HOURS IN REPORTING PERIOO -

' 720 8.016 68.640

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 7.905.9g

'55.455.1

- 13. REACTOR RESERVE. SHUTDOWN HOURS 0.0 0.0 0.0

-=

c720.0

-7.882.6; 54.440.8-14 HOURS GENERATOR ON-LINE

- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 -

0.0

.O.0

=........

=- - --

- 16. GROS $ THERMAL ENERGY GENERATED (MWH)

. 2.224.078.

25.649,2487

- 167.382.713.

17.' GROSS ELECTRICAL ENERGY GENERATED (MWH)-

'711.700'

.. 8.409.020.

54.385.160

18. NET ELECTRICAL' ENERGY' GENERATED (MWH).

. 686.146 8.'113.960)

- 52.154.477.'

.....-s-..

PAGE'1 OF 2

+

+

t.

i t

T e.u

-am u

-mm..i --.cs.-

m.

m 2. me+

-a

-*---+a..a

+ w oree w es

'ea=r.-e 4 m '-

vnwtw

--st---

-t

  • '-,++wwe~T-e rF -A-? e e

.wm-'se ve in Nw

  • v ervreeMed weeis-e

,4 wmab erad hr wre i s

--w-e-4 ew W2e.-. m.u*--

.er.w.m u.u-.--- ia..--

-.a

OPERQTING DGTo REPORT (CONTINUED)

DOCKET NO. 50 - 352

_ _ _. =.

DATE DECEMBER 9, 1993 THIS MONTH VR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 98.3 79.3
20. UNIT AVAILABILITY FACTOR 100.0 98.3 79.3
21. UNIT CAPACITY FACTOR (USING MOC NET) 90.3 95.9 72.0
22. UNIT CAPACITY FACTOR (USING DER NET) 90.3 95.9 72.0
23. UNIT FORCED OUTAGE RATE 0.0 1.7 4.8
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):

STH REFUELING OUTAGE: 1/79/94: 45 DAYS

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

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

FORECAST ACHIEVED INITIAL CRITICALITY 12/19/84 12/22/84 INITIAL ELECTRICITY MID APRIL 85 4/13/85 COMMERCIAL OPERATION IST QTR 86 2/01/86 PAGE 2 0F 2.

.... s

G UNIT SHUTDOWNS AND POWER REDUCTIONS

' DOCKET NO. 50 - 352 UNIT NAKE LIKERICK UNIT 1 DATE DECEMBER 9 1993

^

REPORT MONTH NOVEMBER. 1993 COMPLETED BV PHILADELPHIA ELECTRIC COMPANY JOHN J. MCMENAMIN REPORTS ENGINEER SITE ENGINEERING n

LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3T94

- - - - - - - - - _ _ - - - - - -...... _ - - - - - _.. _ _ - - - - -..... = = - - - - - - = - - -

METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND' CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.

DATE (1)

(HOURS)

(2)

REACTOR (3)

REPORT *

(4)-

(5)

PREVENT RECURRENCE-26 931105 5

000.0 H

4 N/A CH HTEXCH REACTOR POWER WAS REDUCED TO 95% TO REMOVED THE STH FEEOWATER HEATER FROM SERVICE DUE TO COASTDOWN.

27 931114 S

000.0 B

4 N/A HA INSTRU REACTOR POWER WAS REDUCED TO 96% FOR MAIN TURBINE VALVE TESTING.

28 931128 F

000.0 d

4 N/A HA TURBIN REACTOR POWER WAS REDUCED TO 88.5% TO REDUCE HIGH TURBINE BACKPRESSURE.

29 931128 S

000.0 8

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 50% TO-PERFORM CONTROL ROD HYDRAULIC CONTROL.

UNIT MAINTENANCE AND TO PERFORM' CONDENSER CLEANING.

i

. I (1)

(2)'

'(3)'

(4)

F - FORCED REASON METHOD EXHIBIT G ~ INSTRUCTIONS S - SCHEDULED A-EQUIPMENT FAILURE (EXPLAIN)

'1 - MANUAL

.FOR PREPARATION OF DATA B - MAINTENANCE _OR TEST 2 - MANUAL SCRAM.

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

EVENT REPORT (LER)

D - REGULATORY RESTRICTION OTHER (EXPLAIN)

' FILE.(NUREG-0161)

E - OPERATOR TRAINING +' LICENSE EXAMINATION H - OTHER(EXPLAIN)

~ (EXPLAIN).

-(5):'

F - ADMINISTRATIVE G - OPERATIONAL ERROR EXHIBIT I - SAME SOURCE -

t

'(

4

,.s..-',...I.

,-,.-,*.~-#.-.4-e.,t.e.

,m...

~,Es

-c.,-.As

.e e -

...e.,,+-d.-

,.).*%e, er,v %

,..a webi.

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

l 1

Dockst No. 50-353

.)

~Attachm:nt to Monthly..

_j Operating Report for.

' November'1993 Limerick Generating Station Unit 2 November 1 through November 30,'1993 i

I.

Narrative Summary of Operatina Experiences Unit 2 began this operating period at 100% of ratedLthermal power (RTP).

j On November 6, 1993 at 0823 hours0.00953 days <br />0.229 hours <br />0.00136 weeks <br />3.131515e-4 months <br /> power was reduced to 80%~

l RTP for a control rod pattern adjustment and-SCRAM time testing.

Power was. restored to 100% RTP at 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br />.

On November 14, 1993 at 1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br /> power was reduced to 97%

RTP for a centrol rod exercise test and then restored to 100% RTP shortly thereafter.

On November 21, 1993 at 0934 hours0.0108 days <br />0.259 hours <br />0.00154 weeks <br />3.55387e-4 months <br /> power.was reduced to 92%~

Power-was restored to RTP for Main Turbine Valve Testing.

J 100% RTP at 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br />.

l Unit 2 ended this' operating period at'100%-of ratedLthermal-power.

II.

Challences to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief l

Valves during the month of November.

i l

l 1.

i l

I

DVERAGE DQILV UNIT POWER LEVEL DOCKET NO. 50 - 353 UNIT LIMERICK UNIT 2 DATE DECEvBER 9, 1993 COMPANY PHILADELPHIA ELECTRIC COMPANY JOHN J.

MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 MONTH NOVEMBER 1993 DAY AVERAGE DAILY POWER LEVEL DAV AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 1070 17 1065 2

1071 18 1070 3

1070 19 1063 4

1072 20 1071 5

1064 21 1060 6

990 22 1071 7.

1073 23 1075 8

1073 24 1065 9

1073 25 1075 10 1072 26 1074 11 1071 27 1065.

12' 1068 28 1062 13 1069 29 1067 14 1060 30 1071 15 1056 16 1066

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

OPERATING DATA REPORT DOCGET NO. 50 - 353 DATE DECEMBER 9.

1993 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY JOHN J.

MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3794 OPERATING STATUS 1.

UNIT NAME: LIMERICK UNIT 2 NOTES: THERE WAS ONE LOAD DROP 2.

REPORTING PERIOD:

NOVEMBER, 1993 GREATER THAN 20% THIS 3.

LICENSED THERMAL POWER (MWT):

3293 MONTH TO PERFORM CONTROL 4.

NAMEPLATE RATING (GROSS MWE):

1138 ROD PATTERN ADJUSTMENTS 5.

DESIGN ELECTRICAL RATING (NET MwE):

1055 AND SCRAM TIME TESTING.

6. MAXIMUM DEPENOABLE CAPACITY (GROSS MWE): 10 ]

7 MAXIMUM DEPENDABLE CAPACITY (NET WWE):

1055 8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

9.

POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720 8,016 34.152

_~_--___.___

=

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 6.657.8 29,898'6

_=___.

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 720.0 6,546.2 29,202.7
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 2,358,192 20,890.734 92.856,884
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 792,530

.6,916.340 30,669,446

18. NET ELECTRICAL ENERGY GENERATED (MWH) 767.261 6,670,604 29,533.651 PAGE 1 OF 2

O OPERQTING DQTA REPORT (CONTINUED)

DOCKEY NO. 50 - 353

~*

DATE DECEMBER 9, 1993 THIS MONTH YR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 81.7 85.5
20. UNIT AVAILABILITY FACTOR 100.0 81.7 85.5
21. UNIT CAPACITY FACTOR (USING MDC NET) 101.0 78.9 82.0
22. UNIT CAPACITY FACTOR (USING DER NET) 101.0 78.9 82.0
23. UNIT FORCED OUTAGE RATE O.0 2.7 4.2

- _ = _ _ - = - _ - _ - _ _ _

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):
25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUPa
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 08/12/89 08/12/89 INITIAL ELECTRICITY 09/01/89-09/01/89 COMMERCIAL OPERATIO.4 02/01/90' 01/08/90 PAGE 2 OF 2

,... ~

~

.~.-. -. - -..

UNIT SHUTDOWN 5 AND POWER REDUCTIONS DOCKET NO. 50 - 353 UNIT NA%E LI~ERICK UNIT 2 REPORT MONTH NOVEMBER, 1993 COMPLETED BY PHILAOELPHIA ELECTRIC COMPANY JOHN J. MCMENAMIN REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (215) 32T-1200 EXTENSION 3T94 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOwN EVENT CODE CODE ACTION TO NO.

DATE (1)

(HOURS)

(2)

REACTOR (3)

REPORT s (4)

(5)

PREVENT RECURRENCE 43 931106 S

000.0 0

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 80% FOR CONTROL RCD PATTERN ADJUSTMENTS AND TO PERFORM SCRAM TIME TESTING.

44 931114 S

000.0 B

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 9T% FOR CONTROL ROD EXERCISE TESTING.

45 931121 000.0 B

4 N/A HA INSTRU REACTOR POWER WAS REDUCED TO 92% FOR MAIN TURBINE VALVE TESTING.

(1)

(2)

(3)

(4)

F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR-TEST 2 - MANUAL SCRAM.

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

' EVENT REPORT (LER)

D - REGULATCRV RESTRICTION -

4 - OTHER (EXPLAIN)

FILE (NUREG-0161)

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

G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAIN)

EXHIBIT I - SAME SOURCE

- -