ML20236C494
| ML20236C494 | |
| Person / Time | |
|---|---|
| Site: | Limerick |
| Issue date: | 09/30/1987 |
| From: | Alden W, Gropp R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8710270221 | |
| Download: ML20236C494 (8) | |
Text
-
- +-
i
< AVERAGE DAILY UNIT P0HER LEVEL i
j-t.
I k
i.,
DOCKET NO. 352 UNIT LINERICK' UNIT 1 Lj DATE OCTOBER 15, 1987 I
CONPANY PHILADELPHIA ELECTRIC COMPANY ~
R. H. GROPP l
-TECHNICAL' ASSISTANT LICENSINO SECTION NUCLEAR SUPPORT DEPARTMENT i
i TELEPHONE I215) 841-5058 l
'^
l1
.HONTH SEPTEPBER 1987 L
j l
AVERAGE DAILY P0HER LEVEL DAY.
' AVERAGE DAILY PONER LEVEL DAY (PHE-NET)
(PNE-NET 1
.1 -
13f 17 984 2
199' 18 1013 3
345 19 375 4
375 20 0
5 687 21 453
{
-6 767 22 889 7
426 23 976 l
8 0
24 1033 9
3 25 507 1
'10 377 26 346 11 618 27 0
12 891 to 433 i
'13 826 29 892 14 1016 30 843
' 15 1030 16 1014
}
8710270221 870930
$N I
PDR ADOCK 0S000352 1
f R
PDR g/ )
_---_--_-_.-_J
_ ~. - -
i
/
's,
+,
i I
OPERATING DATA REPORT k<.
p 1
DOCKET NO. 50 - 352 6
DATE OCTOBER 15, 1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY I
R. H. GROPP TECHNICAL ASSISTANT.
i LICENSING SECTION l
NUCLEAR SUPPORT DEPARTHENT '
~ TELEPHONE ( 215) 841-5058 -
OPERATING STATUS f
'1." UNIT NAMEt LIHERICK UNIT 1 1 NOTES THE UNIT EXPERIENCED THO.
l l
l 2.' REPORTING PERIDOI SEPTEHBER, 1987 l
FORCED SHUTDOHNS, THREE FORCED l l
l 2 3. LICENSED THERHAL P0HER(19tTil 3293 I
LOAD REDUCTIONS AND THO l-l l
i
' D. NAMEPLATE RATING (GROSS ttlEll 1138 l
SCHEDULED LOAD REDUCTIONS.
l l
l i--
- 5. DESIGN ELECTRICAL RATING (NET HHEll 1055 l
'l I
l l
- 6. HAXIHUM DEPENDABLE CAPACITY '(GROSS HNE ) -1092 l.
l l
l
- 7. HAXIMUM DEPENDABLE CAPACITY (NET HHE) 1055 l
l
' 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUPBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI 9.~P0HER LEVEL TO NHICH RESTRICTED, IF ANY (NET HHE)
- 10. REASONS FOR~ RESTRICTIONS, IF ANY:
THIS HONTH YR-TO-DATE CUHULATIVE
.l i
'I
)
- 11. HOURS IN REPORTING PERIOD 720 6,551 14,567
- 12. NUMBER OF HOURS REACTOR HAS CRITICAL 668.8 3,918.0 10,635.0 j
)
- 13. REACTOR RESERVE SHUTDOHN HOURS 0.0 0.0 0.0 I
i
- 14. HOURS' GENERATOR DN-LINE 587.9 3,717.7 10,353.7
- 15. UNIT RESERVE SHUTD0fti HOURS 0.0 0.0 0.0
'16. GROSS THERHAL ENERGY GENERATED (HHH) 1,447,553 10,841,340 32,439,502
- 17. GROSS ELECTRICAL ENERGY GENERATED (HHH) 440,410 3,462,840 10,589,720 I
l
)
- 18. NET ELECTRICAL ENERGY GENERATED (MHH) 417,352 3,286,835 10,135,685
\\
l PAGE 1 0F 2 L
l l
lC____._____.__.___m_ _ _ _ _ _ _ _ _ _ __i._ _.
';r; ',
- 8
,. ),,'
-OPERATING DATA REPORT (CONTINUED).
DOCKET NO. 50 - 352-
^
?.
s
'2 i
DATE OCTOBER 15, 1987 s
. THIS HONTH-YR-TO.DATE.
CUPULATIVE.
- 19. UNIT SERVICE FACTOR 81.7 56.6 71.1 120.' UNIT' AVAILABILITY FACTOR.
81.7 56.8.
71.1
' 21. UNIT CAPACITY FACTOR (USING MDC NET) '
54.9 47.6
'66.0 i
- 22.: UNIT CAPACITY FACTOR (USING DER NET) 54.9 47.6 66.0
-)
.23. UNIT FORCED DUTAGE RATE 18.3 '
6.4 4.5 J24.'SHUTD06HS SCHEDULED OVER NEXT 6 HONTHS (TYPE, DATE, AND DURATION OF EACH)I
'REFL'ELING OUTAGE k
- 25. IF SHUTDONN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt
~
l ~
' 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL ~ 0PERATION):
FORECAST ACHIEVED.
l INITIAL CRITICALITY 12/19/84-12/22/84-I l
-1
. INITIAL ELECTRICITY HID APRIL 85 4/13/85 i
j COMMERCIAL OPERATION
i 1
l i
l.'
i PAGE 2 0F 2 1
i-l l
i l
I L
i.-
w--
- g f3 i
x -
L D. i J
c
)
,*?
' LNIT SHUTDODNS AND PONER REDUCTIONS DOCKET No. 50 - 352' r
(
UNIT NAME LIHERICK UNIT 1 u.
D DATE OCTOBER 15, 1987 REPORT HONTH SEPTE NER, 1987 COMPLETED BY PHILADELPHIA ELECTRIC COHPANY R. H. GROPP TECHNICAL ASSISTANT e
LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT i
TELEPHONE ( 215) 841-5058 o...........................................................................................................................
l'
'l
. l.-
l HETH00 0F l. LICENSEE lSYSTEHICOMPONENTl CAUSE'AND CORRECTIVE l.
ElTYPElDURATIONlREASONISHUTTING DO&Nl EVENT l CODE 1 CODE l ACTION TO'
$I ?.DATE Tl (Ill-(HOURS)l t 2) l REACTOR (3) l' REPORT # l - ( 4 ) -- l
-(5) l PREVENT RECURRENCE l'
.I
~l
.I I
I I
I I
/8'I 870907 l F l 054.2. l H l 3
l' 87-46 l PA l 777777 l REACTOR SCRAH FOLLOHING A TURBINE TRIP ON HIGH
'l, l>
l.
l
.I l
l l
l HOISTURE SEPARATOR HATER LEVEL.
'I cl 1
l l
l I
il I
- )
L9 i'870913.I F l 000.0 l A l 4
I WA l RS l INSTRU l REACTOR P0HER REDUCED TO REPLACE FAULTY
' l..
l l
l 1
I l
l l ELECTRONIC CARD IN REDUNDANF REACTIVITY l
. l l
l l
l l
l l CONTROL SYSTEM.
I' I-1 I
I I.
I I
I B0'l'870919'l 'F l 038.3^l A~l-3 l
87-48
- 1. HA. I PIPEXX - l REACTOR SCRAM FOLLOHING A TUR8INE TRIP.
j j
i-l l
l l
l
- l l RESULTING FROM A LOSS OF EHC PRESSURE DUE TO l
l ~-
~l<
. l l
1 l
l l
l FAILED PIPING HELD.
~
l-1 l
l l
l l
l l
]
01"l'870922 l' S l 000.0 l F
l' 4
l WA l ZZ l 777777 l REACTOR P0HER REDUCED TO ACCOMMODATE CONTR08.-
~l!
. l~
^l-
-l
'l
'l l
-l l R00 PATTERN ADJUSTMENTS.
'l-
'l I
LI l
.I I
i I
82 l 870925 1 F l 008.3. 1-A l'
4 l
WA l HA l VALVEX l REACTOR P0HER REDUCED AND HAINTAINE; HITH
'l!
'l l
l l.
l l
l l TURBINE HANUALLY TRIPPED TO REPAIR, LEAKING.
,1-
.1 l
l' l
l l
l l EHC CONTROL VALVE SERVO.
l-l
-l I
l l
1 l
l 83 1 870921 i F l 031.2 l H' l 4
i WA I ZZ l 777777 l REACTOR PONER REDUCED AND HAINTAINED NITH
.l, I
l
.I l
l l
l l TURBINE MANUALLY TRIPPED TO REPLACE EHC OIL li i
l l
l 1
-l l
l SOAKED INSULATION AROUND TURBINE CONTROL VALVE =
.' l
- l l
l l
l l
l l
1 l
J i
i l
(1)
(2)
(3)
(4) 7 ' FORCED REASON HETH00 EXHIBIT G - INSTRUCTIONS 1. SCHEDULED A - EQUIPHENT FAILURE (EXPLAIN) 1 - HANUAL FOR' PREPARATION OF DATA B'- MAINTENANCE OR TEST 2 - HANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER)
^
D - RFGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE INUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN) 4 H - OTHER(EXPLAIN)
EXHIBIT I - SAME SOURCE s
i
Y.;:
ji4 f t.
-q :
t p.
'i.
i 'ri-..
. UNIT SHUTDOWNS AND PONER REDUCTIONS DOCKET No. 50 - 352 a
j
(
UNIT NAME LIHERICK UNIT 1 l
DATE OCTOBER 15, 1987
-l REPORT HONTH SEPTEMBER,1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY.
R. H. GROPP
-TECHNICAL ASSISTANT' LICENSING SECTION ~
m NUCLEAR SUPPORT DEPARTHENT TELEPHONE (215) 841-5058 :
b................___........___..___...__..____...___.
l' l
'l.
El i 'HETH00 0F. 1 LICENSEE ISYSTEHlC0HPONENTl CAUSE AND CORRECTIVE l ' l.'
i ITYPE IDURATIONl REASON l SHUTTING DOPNI EVENT l CODE I CODE ^ l ACTION TO M.'.l.~' DATE 'i I ' (1)lII HOURS )1 - ( 21' l REACTOR ( 3 )
l[ REPORT # l >I4) 1-(5) l PREVENT RECURRENCE b..
-l-
.I l'
l
'l i
I I
I
$4 l 870929:l' S l 000.0 L l F: l' 4
l N/A l
ZZ' l 777777 l REACTOR P0HER REDUCED TO ACCOMMODATE CONTROL
'l.
,l.
l.
l l
-l l
l l ROD PATTERN ADJUSTMENTS.
- l l
- .I'.....
.l~
.i
.l:
l l
l l
lt l 132.0.1 l
l l
l l
,l
.i l,
,(ll'
.(2)
(3)
(4) 1 l
h'.FDRCED
' REASON
'HETHOD-EXHIBIT G - INSTRUCTIONS D ' SCHEDULED.
A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA-l
'B'
' MAINTENANCE OR TEST 2 - HANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE i
1
]
C - REFUELING-3 - AUTOMATIC SCRAM.
EVENT REPORT (LER)
I
~D -'RE9ULATORY-RESTRICTION' 4 - OTHER (EXPLAIN)
FILE (NUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION
-1 l.
F. ADMINISTRATIVE (5)
-i L
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER(EXPLAIN)
EXHIBIT I - SAME SOURCE i
l' I
i l'
l'
-l 3
Il l
l l
i L
4 l
l i'
I l
4 Docket No. 50-352 Attachment to Monthly Operating Report for September, 1987 i
Limerick Generating Station Unit 1 September 1, through September 30, 1987 I.
Narrative Summary of Operating Experience The unit began the report period operating at 23% power following startup from the first refueling outage.
Power ascension continued until September 7, 1987.at 1321 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.026405e-4 months <br />, when the Reactor Protection System initiated a full reactor scram from 83% power.
The scram resulted from the main turbine stop valves closing following a turbine trip on high water level in the
'C2' moisture separator drain tank.
The cause was attributed'to a moisture separator level.
control supply air problem.
An Unusual Event was declared as' l
a result of the unplanned shutdown.
The scram was reset and i
the Unusual Event terminated at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br /> and unit start-up operations commenced.
On. September 8, 1987 at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, the unit achieved criticality.
The unit returned to power operation at 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br /> on September 9, 1987.
On September 19, 1987 with the unit operating at 90% power a
[
full reactor scram occurred when the main turbine tripped due J
to low EHC fluid pressure.
Vibration had caused a weld i
failure on the EHC piping and resulted in the low EHC fluid j
pressure condition.
The weld was repaired, the EHC system j
was returned to service and startup commenced.
On September 20, 1987 the unit achieved criticality and was I
returned to power operation at 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> on September 21, 1987.
On September 25, 1987, reactor power was reduced to 21% and the turbine was manually tripped at 1353 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.148165e-4 months <br /> to investigate an EHC system leak.
An 0-ring on the #2 Main Turbine Control valve servo was replaced and the unit returned to service at
)
2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />.
j On September 26, 1987, with the unit operating at 63% power, I
insulation around the #2 Turbine Control valve was discovered smoldering.
The insulation had been oil soaked as a result of the EHC system leak.
Reactor power was reduced to 20% and the turbine was manually tripped at 1833 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.974565e-4 months <br />.
The insulation was replaced and the unit returned to service September 28 at 0148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br />.
Power ascension continued until excessive vibrations were discovered on EHC piping at the main turbine control valves.
Reactor power was reduced to 83% power and piping vibrations subsided.
The unit continued to operate at this level for
l. J :
m.
? *,
z L.
'. Y' Docket No'.
50-352' E' [*L
. Attachment..to. Monthly Operating' Report for m
September,;1987?
theiremal'nder>of..the-report period wtiile't'he investigation'>
-into the'EHC-piping ~. vibration conti'nues.
II.. Challenges'to Relief-Valves There.were-no' challenges to the-. Main. Steam Safety-Relief:
valves.during the: month.
f
- e t
4 1
)
I l
l I
_________a
lc-
/V PHILADELPHIA ELECTRIC COMPANY I
2301 M ARKET STREET I
P.O. BOX 88599 -
PHILADELPHIA A. PA,19101 (2im e4i 4ooo October-19,-1987
)
Docket No.-50-352 I
I Director
-Office of Resource Panagement U.S. Nuclear Regulatory Commission 1
1 Washington, DC 20555 8C m 4
Z l
' Attention:
Document Control Desk N
b.
T
SUBJECT:
Limerick Generating Station y E Monthly Operating Report m
A
\\
c Gehtlemen:
d I
Enclosed is the monthly operating report.for Limerick Unit 1 for the month of September 1987, forwarded pursuant to Technical. Specification 6.9.1.6.
We regret the late submittal of i
this report and any inconvenience the delay may have caused.
1 I
Very truly yours, j
4 l
W. M. Alden Engineer-In-Charge Licensing Section Nuclear Support Department
' Attachment I
Director, Office of Inspection & Enforcement, USNRC (12 copies) cc:. William T.
Russell, Administrator, Region I, USNRC q
E. M. Kelly, Senior Resident Site Inspector i
Mr. David E. Ney, PA Dept. of Envir. Resources i
Mr.
P. A. Ross, NRC (2 copies) l INPO Records Center i
_