ML20011D491
| ML20011D491 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/30/1989 |
| From: | Jerome Murphy PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20011D484 | List: |
| References | |
| NUDOCS 8912270317 | |
| Download: ML20011D491 (12) | |
Text
-
e 3903012450 l
Docket No. 50-352 l
Attachment to Monthly Operating Report for November 1989 l
c l
Limerick Generating Station l
Unit 1 l
November 1 through November 30, 1989 l
l I.
Narrative Summary of Operatina Exoeriences Limerick Unit 1 began the month of November in Operational Condition (OPCON) 1 (power < operation), at a nominal 100% of; rated thermal power.
On November 2, the
'1A' Reactor Feed Pump (RFP) tripped when personnel working around the feed pump jarred a vibration probe.
The feed pump _ trip resulted in a i
power reduction to 68%.
The reactor was restored to 100% on November 4 following a control rod pattern adjustment.
Later i
the same day, reactor power _ was reduced to 50% so that l
maintenance personnel could repair an Electro-hydraulic
)
Control (EHC) System fluid leak on the #2 turbine control valve.
During this load drop the
'1B' circulating water box was drained and cleaned, scram time testing was performed on 26 control rods, and the control rod pattern was adjusted.
Following successful repair of the'EHC system fluid leak,
{
power was restored to 100%.on November 5.
On November.16, reactor power was reduced to 95% to reduce main turbine back l
pressure.
Later the same day, reactor power was - reduced
.j further to 85% in order to support a control rod pattern adjustment.
Reactor power was restored to 100% on November 17.
Limerick Unit 1 ended the month of November in OPCON 1 at a nominal 100% of rated thermal power.
l 1
Operational events that occurred during the month of November I
l included:
On November 2, the
'1A' RFP tripped on high vibration when personnel working around the feed pump inadvertently jarred a vibration probe.
A 75% recirculation pump run l
back was automatically initiated due.to the RFP pump j
trip. The unit was stabilized at 68% reactor power.
On November 19, the Reactor Water Cleanup (RWCU)Lsystem-i isolated when readings were being taken in the Auxiliary Equipment Room for the Daily. Surveillance Log.
A Division IV Steam Leak Detection Isolation signal was generated, which closed the outboard RWCU isolation valve-and subsequently tripped the RWCU pump due to low flow.
Instrument and Controls (I&C) personnel conducted an investigation of the problem and determined that the READ switch was defective.
The faulty temperature switch was replaced and declared operable on November 20.
The i
8912270317 891234
{DR ADOCK 05000352 PDC l
l 3903012450 isolation was caused by a faulty READ ' switch for the '1B' Nonregenerative Heat Exchanger area temperature.
On November 20, during the start of the
'1B' Residual Heat Removal pump, the "201-D12 Bs Breaker Control Power Undervoltage" status light illuminated. An investigation into the cause revealed that a fuse' feeding the bus feeder undervoltage relays had blown.
The '1B' RHR pump was subsequently restarted with no further incidences.
On November 20, the Refuel Floor HVAC isolated due to a I
low differential pressure isolation signal.
The Standby
[
Gas Treatment System (SGTS) initiated and operated per design. The isolation. was caused by high ambient wind i
conditions.
The SGTS was secured when the high winds
- subsided, j
On November 23, the RWCU system isolated on high differential flow.
An investigation revealed that a differential flow indicator indicated 52 gpm after the isolation.
I & C repaired a flow switch and the corresponding channel was declared operable following satisfactory completion of a functional test.
The RWCU isolation was - reset and the system was returned to service.
II.
Challences to Main Steam Safety Relief Valves There were no _ challenges to the Main Steam Relief Valves-during-the month of November.
I i
i
______m
t 3903012450 5
1 AVERT.GE 0AILY UNIT POWER LEVEL i
DOCKET NO. 50 - 352 UNIT LIMERICK UNIT 1 I
0 ATE DECEMBER 14, 1989 COMPANY PHILADELPHIA ELECTRIC COMPANY j
J. J.
MURPHY REPORTS SUPERVISOR PROJECTS DIVISION LIMERICK GENERATING STATION t
TELEPHONE (215) 327-1200 EXTENSION 3752 MONTH NOVEMBER 1989 DAY AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 1035 17 1018 2
861 18 1040 3
1003 19 1062 4
801 20 1009 5
1029
- 21 1038 6
1031 22 1034 7
1033 23
,1039 8
1036 24 1040 9
1021 25 1030' 10 1037 26 1028 11 1037 27 1035 12 1017 28 1023 13 1028 29 1032 14 1014 30 966 15 1012 16 1025
P 3903012450 OPERATING DATA REPORT DOCKET NO. 50 - 352 DATE DECEMBER 14 1989 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY 1
.J.
J. MURPHY-REPORTS SUPERVISOR PROJECTS DIVIS10N' LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3752 OPERATING STATUS
- 1. UNIT NAME: LIMERICK UNIT 1 NOTES: THERE WERE TWO LOAD
- 2. REPORTING PERIOD: NOVEMBER. 1989 REDUCTIONS GREATER THAN
- 3. LICENSED THERMAL POWER (MWT):
3293 20%
O. NAMEPLATE RATING (GROSS MWE):
1138
- 5. DESIGN ELECTRICAL RATING (NET MWE):
1055
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1092
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1055 B.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) $1NCE LAST REPORT. GIVE REASONS:
l
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTIONS. IF ANY:
THIS MONTH VR-TO-DATE CUMULATIVE 11 HOURS IN REPORTING PERIOD
.........720 7.991 33.551 3
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 5.015.5
'26.359.0
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14 HOURS GENERATOR ON-LINE 720.0 4.869.9 25.902.6
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0
' 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 2.328,667 14.517.173 75.314.930
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 757.440 4,673.900 -
24.355.570
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)-
729.984
'4.413.651 23~.256.139 PAGE 1 0F 2
s 3903012450 i
OPERATING DATA REPORT (CONTINUED)
DOCKET NO. 50 - 352 DATE DECEMBER 14 1989 THIS MONTH YR-TO-DATE CUMULATIVE
- 19. UNIT SERVICE FACTOR 100.0 60,9 77.2
- 80. UNIT AVAILABILITY FACTOR 100.0 60.9 77.2
- 31. UNIT CAPACITY FACTOR (JSING MDC NET)-
96.1 52.4 65.7 I
- 28. UNIT CAPACITY FACTOR (USING DER NET) 96.1 52.4 65.7
- 23. UNIT FORCED OUTAGE RATE 0.0 0.0 3.0 24 $HUTD,0WNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):
- 85. 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 OF 2 i
}{ C){} } {} j "
UNIT SHUTDOWNS AND POWER REDUCT20NS DOCKET NO. 50 - 352 E
UNIT NAME LIMERICQ UNIT 1 DATE DECEMBER 14, 1989
~*
REPORT MONTH NOVEMBER. 1989 COMPLETED BV PHILADELPHIA ELECTRIC COMPANY J. J. MURPHY REPORTS SUPERVISOR PROJECTS DIVISION LINERICK GENERATING STATION
' TELEPHONE (215) 32T-12OO EXTENSION 3752 METHOD OF LICENSEE i 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 1
7 891102 F
000.0 H
4 l
N/A CH PUMPXX THE 1A REACTOR FEED PUMP TRIPPED WHEN PERSONNEL i
DISTURBED A VIBRATION PROBE.
IT CAUSED A 32%
l POWER REDUCTION. _.THE OPPORTUNITY WAS TAKEN TO PERFORM A CONTROL ROD PATTERN ADJUSTMENT.
8 891104 S
000.0 B
4 N/A HB L ZZZZZZ REACTOR POWER WAS REDUCED 50% TO REPAIR AN EHC LEAK ON.THE #2 TURBINE CONTROL VALVE.
(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 4 - OTHER (EXPLAIN)
FILE (NOREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER(EXPLAIN)
EXHIBIT I - SAME SOURCE w
- - -- - = - -
3903012450-Docket No. 50-353 Attachment to Monthly Operating Report for November 1989 Limerick Generating Station Unit 2 November 1 through November 30, 1989 I.-
Narrative Summary of Operatina Exneriences Limerick Unit 2-began the month of November in Operational i
Condition (OPCON) 1 (power operation) at a nominal 73% of rated thermal power.
On November 10 the Unit 2 reactor automatically shut down following a ge,nerator lockout.
The generator lockout was caused when the '1A' phase differential relay tripped at an incorrect setpoint.
The phase differential relays were recalibrated, and the Unit j
subsequently entered OPCON 1 on November 14.
On November 21, reactor power was sustained at 100% for the first time.
On November 23, the
'2B' reactor feed pump tripped and a subsequent reactor recirculation pump run back occurred resulting in a reduction to 60%.
A defective vibration card was determined to be the cause-and the '2B' reactor feed pump was returned to service.
Reactor power was restored to 100%
on November 23.
Limerick Unit 2 ended the month of November in OPCON 1 at a nominal 100% of rated thermal power.
Operational events that occurred during the month of November included:
i i
On November 2, the '2A' and '2B' recirculation pumps were tripped in accordance with startup testing.
There were no unexpected occurrences.
Following completion of the
^;
test, the pumps were returned to service.
t On November 10, the Reactor Water Cleanup (RWCU) system isolated when steam leaking by the Regenerative Heat Exchanger safety relief valve tripped the Division IV steam leak detector.
A second isolation occurred on I
differential flow when the system was placed in service to verify that the valve was leaking.
The system was subsequently blocked for valve repair. The safety relief valve was removed and a blank flange was installed under a temporary modification.
The reactor automatically shut down following a generator lockout.
The lockout was activated by the
'A' phase differential current relay.
The setpoint on the differential current relays were incorrect due to an incorrect calculation.
The relays were recalibrated and tested before the unit was returned to service.
l 3903012450L On November 11, the High Pressure coolant Injection (HPCI) system was declared inoperable after the system operated erratically following an automatic reactor shut down.
While operating on minimum-. flow, after the shutdown, HPCI tripped six times on overspeed within one minute before being secured by an operator.
This cyclic operation was abnormal and could have caused a HPCI failure if it had been allowed to continue. Subsequently the HPCI ramp generator control loop was adjusted and HPCI tested.
During HPCI testing a seal leak was observed on the booster pump.-
HPCI was blocked on November 15, and the seal leak was repaired.
HPCI was subsequently tested satisfactorily at 200 pounds reactor pressure.
HPCI was tested again satisfactorily at approximately 920 pounds reactor pressure.
On November 23, the '2B' Reactor Feed Pump (RFP) tripped causing a reactor recirculation pump runback signal. The Test Engineers found the trip-cause to be a defective card which receives inputs from the RFP's low pressure bearing vibration probe.
A Temporary Circuit Alteration was installed to remove the high vibration trip function j
from the probe.
The alarm functions still operate properly.
The
'2B' RFP was returned to service.
On November 27, the
'2C' RFP was tripped as-part of the startup test program along with the subsequent reactor recirculation pump runback. Reactor level decreaFed from-
+35 inches to +27.5 inches in approximately.30 seconds.
Following the reactor recirculation pump runback, peak reactor level was 342 inches and reactor power decreased t
to 70%.
When all required data was obtained, the
'2C' RFP was returned to service.
The reactor recirculation pump runback signal was reset and a
control rod adjustment was made.
Reactor power was then' returned to 100%.
II.
Challences to Main-Steam Safety Relief Valves There were no challenges to the Main Steam Relief Valves
{
during the month of November.
j l
3903012450 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 352 UNIT LIMERICK UNIT 2 DATE DECEMBER 14, 1989 COMPANY PHILADELPHIA ELECTRIC COMPANY J. J. MURPHY REPORTS-SUPERVISOR PROJECTS DIVISION LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3752 MONTH NOVEMBER 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 727 17 716 2
525 18 1018L 1
3 689 19 854 4
826 20 944 i
5 887 21 1040 6
1016 22 1066 7
1020 23 818 8
1041 24 1073 i
9 1023 25 1116 10 595 26 1032 11 0
27 1035 12 0
28 1063 13 0
29 1074 i
14 0
30 1070 15 0
16 248 i
I 1
i
?-
3903012450 OPERATING DATA REPORT DOCKET NO. 50 - 353
_Dess1@u..M 19M..........
COMPLETED BY PHILADELPHIA ELECTRIC COMPANY J. J. MURPHY REPORTS SUPERVISOR PROJECTS DIVISION LIMERICK GENERATING STATION TELEPHONE'(215) 327 1200 EXTENSION 3752 OPERATING STATUS
- 1. UNIT NAME: LIMERICK-UNIT 2 NOTES: A FULL POWER LICENSE
~ J
- 2. REPORTING PERIOD:
j o ggggy, 1_989,,,___,, _
WAS ISSUED ON 8/25/09.
- 3. LICENSED' THERMAL POWER (MWT):
THE STARTUP TESTING 37gg 4 NAMEPLATE RATING (GROSS MWE):
1138 PROGRAM IS IN PROGRESS.
i 1
- 5. DESIGN ELECTRICAL RATING (NET MWE):
1055 COMMERCIAL OPERATION !$
- 6. CAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
EXPECTED IN THE FIRST
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
OUARTER OF 1990.
8.
IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS NUMBER-3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
j
'I
- 9. POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
1 THIS MONTH VR TO-DATE CUMULATIVE -
- 11. HOURS IN REPORTING PERIOD
...... 7 2 0..
....2.t
- 52. 5
... j(gggg,5 6
1
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL
...... 6.33 1
--.. 2_,2 0. 7 5
.. - - - -.7.. 5 2,20
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14 HOURS GENERATOR ON-LINE
..... 5.87 3
....1. 56.5 9
__.1_,56_5 9 3
- 13. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH)
.I.t.7 8.1.74 2..
3.$ 129.g.86 4
_3.,.129.,.686. 4 6
6
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) j
.. 561.1.60..
.. 9 8 3. 3.15_0..
. 33_3,,(qq..
-i 2
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
_ _ _g)9,0y 9_ _
,,,gg7,3p3,,
,, y,3,7,,Qgl,,
i i
PAGE 1 0F 2 j
i a
l l
r
. 3903012450 OPERATING DATA REPORT (CONTINUED)
DOCKET NO. 50 - 353 DATE....De c e mhe.r. 14,.19AS.......
THIS MONTH ~
YR-TO-DATE CUMULATIVE'
-19. UNIT SERVICE FACTOR
,,,,81 Q,,,,
,,,,, } }, 0 -
-~})L,Q,,,
t
- 20. UNIT AVAILABILITY FACTOR w-is 21 UNIT CAPACITY FACTOR (USING MDC NET)
- 32. UNIT CAPACITY FACTOR (USING DER NET) w
- 23. UNIT FORCED OUTAGE RATE w
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE,.AND DURATION OF.EACH):
INITIAL POWER ASCENSION TESTING !$.IN PROGRESS MAINTENANCE / SURVEILLANCE TEST'0VTAGE. 12/01/89.' 3' WEEKS
- 25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP'
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL 0PERATION):-
FORECAST ACHIEVED-INITIAL CRITICALITY
_jgg ggg9
.g7 g[gp INITIAL ELECTRICITY
. 9./.01./.8.9
. 9./.01./.8. 9..
-COMMERCIAL OPERATION
. 2./.01./.90.:
Q NOT APPLICABLE PRIOR TO COMMERCIAL OPERATION l
4
'PAGE 2 0F 2-t
,, m 1 M.,
l 3903012450 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 353 UNIT NAME LIMERICK UNIT 2 DATE DECEMBER 14 1989 REPORT MONTH NOVEMBER. 1989 COMPLETED BV PHILADELPHIA ELECTRIC COMPANY J. J. MURPHY REPORTS SUPERVISOR PROJECTS DIVISION LIMERICK GENERATING STATION TELEPHONE (215) 327-1200 EXTENSION 3752
___-_=----
_ =_
l METHOD OF l LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE ' DURATION REASONISHUTTING DOWN!
EVENT CODE CODE ACTION TO NO.
DATE (1),
(HOURS)
(2) l REACTOR (3) l REPORT P (4)
(5)
PREVENT RECURRENCE 9
891002 S
000.0 l
8 4
N/A CB PUMPXX THE 2A AND 28 REC 1RC PUMPS WERE TRIPPED CAUSING APPROX 25% LOAD REDUCTION AS PART OF THE STARTUP TEST PROGRAM.
l 10 891010 F
132.T H
3 2-89-013 1 ED RELAYS THE REACTOR SCRAMMED FOLLOWING A GENERATOR l
LOCMOUT.
IT WAS CAUSED BY INCORRECT SETPOINTS l BEING USED ON THE DIFFERENTIAL CURRENT RELAY.
i 11 891019 5
000.0 B
4-N/A CB i PUMPXX
'l A SINGLE RECIRC PUMP-TRIP AND PROGRAM TESTING l
I DURING POWER CHANGES WAS PERFORMED AS PART l
OF THE STARTUP TEST PROGRAM.
12 891023 F
000.0 A
4 N/A CH '
PUMPXX' 2B REACTOR FEED PUMP TRIPPED DUE TO A DEFECTIVE l
VIBRATION CARD.
13 891027 5
000.0 B
4 N/A CH PUMPXX THE 2C REACTOR FEED PUMP WAS TRIPPED AS PARTA OF THE STARTUP TEST PROGRAM.
g 132.7
-l 1
l (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 SHEITS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER)
D - REGULATORY RESTRICTION
~
4 - OTHER (EXPLAIN)
FILE (NUREG-0161)
'E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL-ERROR (EXPLAIN)
H - OTHER(EXPLAIN)
-EXHIBIT I - SAME SOURCE
' ~ ' ' ' ' ' ' ' ' '
' " ' ~ ~
~ ~ '
~
- +.. - -.. - - - - ~ - = = = ~ - - - - - - - - -
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