ML20062B696
| ML20062B696 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/30/1990 |
| From: | Baron M, Miller D PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9010260056 | |
| Download: ML20062B696 (14) | |
Text
-
- CCN 90'-14187 puo.Nu r
PillLADEI.Pi1% ELECTRIC COMPANY sd,kN )
PI:ACil DOT 1DM AR)MIC POWI:R STATION
/
R. D 1. Inox 208
%gmjafM Delta, lYntghania 17314 renoe morrow-ine comia os s u nu w e (717) 4 4 7014 D. It Miller. Jr.
Vice Prendent october 15, 1990 Docket Nos. 50 277 50 278 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
SUBJECT:
Peach Bottom Atomic Power Station Monthly Operating Report Gentlemen:
Enclosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of September 1990 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.
Siricerely, ft h 8. Ahllew ffchv,, pn) i Di3M/ AF/JklC/bRM/MJB: cme Enclosure ec:
R.A. Burricelli, Public Service Electric & Gas T.M. Gerusky, Commonwealth of Pennsylvania J.J. Lyash, USNRC Senior Resident inspector R.
McLean, State of Maryland T.T. Martin, Administrator, Region I, USNRC i
li.C. Schwemm, Atlantic Electne J. Urban, Delmarva Power
{
INPO Records Center 9010260056 900930 ADOCK 050 g 7,,
q PDR R
[.
CGNO.NRC
(
06034 I s\\
~-
{
,0
~ NRC Monthly Operations Summary Peach Hottom Atomic Power Station September 1990
.UtdL1 The unit began the month shut down with repairs to the level transmitters for the 2 "B" reactor level head chambers nearing completion. The unit was placed in Startup on September 2. On September 6, with power nt - 0 26%, hydraulic fluid began leaking from the #1 main turbine bypass valve. Power was reduced and the turbine was tripped.The reactor was placed in the refuel mode for repairs to the bypass valve and repair of a steam leak on the recombiner steam line drain.
The unit was placed in the startup mode on Septcmber 8, and the unit achieved 80% power by September 11.
~
Except for the rod pattern adjustment on September 15, power was held at nominal 80% until September 30 :
because of high copper content in the feedwater and for completion of scheduled maintenance on the'2 'C'.
condensate pump. On September 30, power was reduced to 60% in support of maintenance on the A2 and B2 waterboxes.
On the evening of September 16, the unit experienced a loss of feedwater heating and a positive reactivity _.
Insertion when lightning struck the #3 startup source breaker. Extraction steam was restored and the breaker was closed by normal procedure the same evening.
i A condensate demineralizer backwash valve problem was discovered on September 17. It was causing improper precoat and was contributing to rising copper leds in feedwater. The valve was repaired on September 19, and copper was below 0.3 ppb by September 24.
The waterbox repairs were completed on September 30, and the 2C condensate pump was returned to service on September 31. The unit ended the. month at nominal 81%.
'3 y
The unit began the month v 100% power. On September 6, power was reduced to 65% for waierbox testing On the same day, the 'B' reactor Iced pump turbine control linkage failed. Power was further reduced to'43%
for waterbox leak repairs, which were completed by September 9, as was the repair of the reactor feed pu
+
turbine control linktc Power reached 80% on September 10, but was then reduced to less than 50% until i
September 12 because of feedwater copper concententions greater than 0.3 ppb. Power reached 100% on September 13, after copper levels were sufficiently reduced.
i j
On the evening of September 16, the unit experienced a loss of feedwater heating and a positive reactivity insertion when lightning struck the #3 startup source breaker. Extraction steam was restored and the breaker was closed by normal procedure the same evening. Except for the brief reactivity insertion, power remained at j
100% through the end of the month.
}
1
(
CC0990.NRC
1 Docket No. S271 Attachment to Monthly Operating Report for September 1990 ->
_UN:T 2 EFUEl.1NG INFORM ATION 1.
Name of facility:
i l'ench IMtom Unit 2 2.
Scheduled date for next refueling shutdown:
January 12,1991 3.
Scheduled date for restart following refueling:
March 21,1991 m
4.
Will refueling or resumption of operation therefore require a technicai specification change or other_
license amendment?.
3,,,,
m.
If answer is yes, what, in general, will these be?
Safety limit MCPR for cycle 9.
.1 i
5.
_ Scheduled date(s) for submitting proposed licensing action and supporting information:.
January 1991 6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
i Resolution of licensing issues associated with lead fuel assert.b!!es from new fuel vendors is pending.
7.
The number of fuel asse.mblics (a) in the core and (b) in the spent fuel storage pool:
(a)
Core 764 Fuel Assemblics (b)
Fuel Pool 1734 Fuel Assemblics,58 Fuel Rods CCOMNRC e
a.
- l Docket No. 50-277 :
)
Attachment to Monthly Operating i.
,. Report for September 1990.
Page 2 UNIT 2 REFUELING INFORM ATION (Continued) 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage '
capacity that has leen requested or is planned, in number of fuel assemblies:
The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblics.
9 The. projected date of the last refueling that can be discharged to the spent fuel pool assuming thei
- present capacity: -
September 2003 without full core offload capability.
J
. September 1997 with full core offload capability.
i i
j 9
g L
e tm V
\\
g e
N e
s v
i f
i CC0990.NRC
1 Docket No. 50-278
. Attachment to -
)
' Monthly Operating
. JReport for September 1990 -
4 LIND'3 REFUELING INFORMATION 1.
Name of facility:
1 Peach Ilottom Unit 3 J
2.
Scheduled date for next refueling shutdown:
Reload 8 scheduled for August 31,1991 -
3.
Scheduled date for restart following refueling
- r Restart following refueling scheduled for November 29,1991 4.
Will refueling or resumption of operation ~ thereafter require a technical specification change or other.
license amendment?
~
Yes.
If answer is yes, what, in general, will these be?
Safety limit MCPR for cycle 9 fuel.
4 5.
Scheduled date(s) for submitting proposed licensing action and supporting information:'
August 1991 6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating -
procedures:
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a)
Core 764 Fuel Assemblies l
(b)
Fuel Pool - 14% Fuel Assemblics,6 Fuel Rods CCD990.NRC i.
l..
1
' Docket Nd. 50-278 i
Attachment to Monthly Operating Report for September 1990
- Page 2 i
UNIT 3 REFUELING INFORMATION (Continued) 8.
The present licensed spent fuel pool storage capacity and.the side ' f any increase in licensed storage M. '
o capacity that has been requested or is planned, in number of fuel assemblies:
The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblics, Modification '
of the fuel pool is expected to be complete in the fourth quarter of 1990.
t 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the'-
present capacity:
With the current fuel pool capacity (prior to the completion of the fuel pool rcracking modification):
September 1996 without full core offload capability.
End of next cycle with full core offload capability (est. January 1991).
With increased fuel pool capacity (subsequent to the completion of the fuel pool rcracking modification):
September 2004 without full core offload capability.
~
September 1998 with full core offload capability.
)
.}.
I a-ei s.p#
s
, d,.
_ff s - ;-
l~
. L:
s i
l i
t l
CC099aNRC q
1
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 277 UNIT PEACH SOTTOM UNIT 2 DATE OCTOBER 15,'1990 COMPANY PHILADELPMIA ELECTRIC COMPANY' M. J. BARON
~
SUPERVISOE cREPORTS GROUP.
. PEACH 80' TOM ATOMIC POWER STATION IELEPHONE (717) 456-7014 EXT. 3321 MONTH SEPTEM8ER 1990
-. +
'u DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 0
17 821
^^
2 0
18 823 3
0
,19 816
~
-i.
X' 4
0 20 824' 5
10 2i 817 6
-57 22
- 822
-..i.
7 0
23 838 8
0
- 24
- 856 9
101 25 847 i
10 701
.26 851 11 786 27 843 12 793 28 847 13 857 29 843 4
14 828 30 843 15 751 16 817 l
e.+:
e
+
AVERAGE DAILY UNii POE R LEVEL" o
DOCKET NO. 50 - 278 t
UNIT QCN BOTTOM UNIT 3 P4fE OCiceER 15, 1990 CfAPANY PHILADELPHIA ELECTRIC COMPANY-M. J. BARDW,
$UPERVISOR-3 REPORTS GROUP'.
PEACH BOT 10M ATOMIC POWER STATION I-
>s TELEPHONE (717) 456-7014 EXI. 3321 l
^
~' ~
^'
MONTH $EPTEMBER 1990 DAY AVERAGE DAILY POWR LEVEL DAY AVERAGE DAILY POWER LEVEL 2
(MWE-NET)
-(MWE-NET) 1 1046 17 1051 2
1050 18 1062
^
3 1045 19 1051 e
i 4
1036 20 1063 5
1051 21 1059 i
6
.750 22 1059- -
,j
~~
7 627 23 1067 8
384 24 1063
,],1 9
423 25 1059-10 717 26 1063 l
11 452 27 1063 12 836 28 1055 13 1021 29
-1059 14 1051 30 1059 15
-1055 16 1040 l
\\
m
B j
OFERATING DATA REPORT DOCKET No. 50 - 277 DATE OCT0eER 15, 1990 COMPLETED IT PHILADELPHIA ELECTRIC COMPANT' M. J. BARON
- SUPERvlSOR
. REPORTS GROUP PEACN BOTTOM ATOMIC POWER STAfl0Ni TELEPHONE (717) 456-7014 EXT. 3321l p
OPERATING STATUS
- 1. UNIT NAME: PEACH BOTTOM UNIT 2 NOTES:
~
- 2. REPORTING PERIOD SEPTEM8ER, 1990 a L""
j "y
'+
- 3. LICENSED THERMAL POWER (MWT):
3293 y
v.
- 4. NAMEPLATE RATING (GROS $ MWE):
1152
- 5. DESIGN ELECTRICAL RATING (NET MWE) "
- 106,
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):
1055' b-
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH.7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED,17 ANT,(NET _ MWE).
-10. REASONS FOR RESTRICTIONS, IF ANY l
~ '
^
3
-l
,,n 7
4 THIS MONTH
.YR-TO-0 ATE'
-CUMULATIVE "
- 11. HOURS IN REPORTING PERico 720
- 6,551
~142,367:
m
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 568.4 5,049.7 84,577.0:
e
- 13. REACTOR RESERVE SHUTOOWN HOURS 0.0
' O.0
~0.0'
~
l
- 14. HOURS GENERATOR ON-LINE 526.1 4,897.5
- 81,502.8
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0
'0.0 0.0'
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1,371,864 14,599,704 239,895,897.-
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 433,500 4,787,600 78,847,490
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 416,317 4,606,617 75,461.466
-PAGE.1 0F 2
[
i
,g i
='
\\
OPERATING DAIA RfPORT (CONTINUED)
DOCKET Wo. 502-277 l
DATE OCTOBER 15, 1990 THit MONTH YR-TO-DATE CUMULATIVE i
- 19. UNIT SERVICE FACTOR
' 73.1 74.8
.57.2
- 20. UNIT AVAILABILITT. FACTOR
-73.1
.74.8.,..
- 57. 2.,
- 21. UNIT CAPACITT FACTOR (U$ LNG MDC NET):
. 54.8 66.7 50.2
[
i
- 22. UNIT CAPACITY FACTOR (USING DER NET)
- 54.3 66.0 49.8 ~.
a
- 23. UNIT FORCED OUTAGE RATE
- 26.9
-16.3
' 14 ~. 6 ;.
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TTPE, DATE AND DURATION OF EACH)t,
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERAil0N)'t
' FORECAST.. ACHIEVED INITIAL CRITICALITT:
09/16'/73' INITIAL ELECTRICITY -
02/18/74 COMMERCIAL OPERAT!ON 07/05/74 a
<ps
~+
s
- +
~f h
4 g
+
tes e
+ me e[yd E.[
3 4
g j
- PAGE 2 0F 2-i.
b
i 4
f OPERAflNG DATA REPORT'
-DOCKET Wo. 50 - 278 1
DATE OCTOBER 15, 1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY-t il M. J. BARON
-l SUPERVISOR REPORTS GROUP PEACM BOTTOM ATOMIC POWER STATION
'~
TELEPHONE (717) 456-7014 EXT. 3321 -
OPERATING STATUS
- 1. UNIT NAME: PEACN BOTTOM UNIT 3 NOTES:
- 2. REPORTING PERIOD: SEPTEMBER, 1990 -
' a
~
I
- 3. LICENSED (HERMAL POWER (MWT):
, 3293
- 4. NAMEPLA'E RAflWG (GROSS MWE):
1152
- 5. DESIGN ELECTRICAL RATING (NET MWE):-
1065
- 6. MAXIMull DEPENDA8LE CAPACITY (GROSS MWE): 1098
- 7. MAXIMUD DEPENDABLE CAPACITY (NET MWE): _1035
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS.(ITEMS NUMBER 3 THROUGH,7).SINCE LAST REPORT, CIVE REASONS:-
i
- 9. POWER LEVEL TO WHICH RESTRICTED, IF. ANY,(NET MWE):
m
~
- 10. REASONS FOR RESTRICTIONS, IF ANY.
I'
~ '"
1 THIS MONTH iTR-TO-DATE iCUMULATIVEl
- 11. HOURS IN REPORTING PERIOD 720 6,551 138,263~
- 12. NUM8ER OF HOURS REACTOR WAS CRITICAL
.720,0
'6,260.0.
83,418.8 I
- 13. REACTOR RESERVE SHUTDOWN HOURS
'0.0
'0.0
' O.0 '
- 14. HOURS GENERATOR ON-LINE 720.0 6,147.4 80,549.6
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 l
'0.0 0.0 '
- 16. GROSS THERMAL ENERGY GENERATED (MWN) 2,155,488 18,929,909 235,092,778
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 707,500 6,226,900 77,099,032
- 18. NET ELECTRICAL ENERGY GENERATED (MWH).
681,983 6,010,295
- 73,852,863' PAGE.1 0F 2
. i.
r
4 I
OPERATING DATA REPORT (CONTINUED)
' DOCKET Wo. 50'- 278 '
' i DATE OCTosta 15, 1990 TMil MONTH YR-10-0 ATE CUMULATIVE
- 19. UNIT $ERVICE FACTOR 100.0 93.8 58.3
- 20. UNIT AVAILABILITT FACTOR 100.0=
93.8
! 58.3 '
91.5 88.6 51.6 N
- 22. UNIT CAPACITY FACTOR (USING DER NET) 88.9 86.1 50.2
- 23. UNIT FORCED OUTAGE RATE 0.0 6.2 12.8
- 24. $HUTDOWNS $CHEDULED OVER NEXT 6 HONTHS (TYPE, DATE, AND DURATION OF EACH):
NID4YCLE MAINTENANCE OUTAGE STARTING OCTOBER 27,
$CHEDULED FOR 21 DAYS.
+
- 25. IF $HUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP
- 26. UNITS IN TEST STATU$ (PRIOR TO COMMERCIAL _0PERATION):. FORECAST -ACHIEVED i
INITIAL CRITICALITY J08/07/74 INITIAL ELECTRICITY -
09/01/74 s
COMMERCIAL OPERATION 12/23/74 p
4 4
4 4
T b
. L
't 1PAGE 2 0F 2 l
l
t e
l 3
t p
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50 - 277 UNIT NAME PEACH BOTTOM UNIT 2.
DATE OCTOBER 15, 1990; REPORT MONTH SEPTEMBER,1990' COMPLETED BT PHILADELPHIA ELECTRIC COMPANT M. J. BARON SUPERVISOR
, REPORTS GROUP-
+.
PEACH BOTTOM ATOMIC POWER STAfl0N '
, TELEPHONE (717) 456-7014 EXT. 3321
.s METH00 0F LICENSEE-STSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURAfl0N REASON SHUTTING DOWN EVENT CODE CODE ACTION TO No.
DATE (1)
(HOURS)
(2)
REACTOR (3)
REPORT #
(4)
(5)
PREVENT RECURRENCE 15 900901 F
116.3 A
2 2-90-21 LID INSTRU REACTOR LEVEL: INSTRUMENTATION THAT USES 2B REFERENCE LEG DETERMINED TO BE INOP.:
REACTOR WAS SHUT.DOWN.
16 900906
-F 77.3
'A
'2' N/A.
REACTOR WAS SHUT DOWW.'
17 900913 F
0.0
-H 4
. N/A HH ZZZZ22 HICH COPPER. CONTENT IN THE CONDENSATE.
REACTOR WAS NOT SHUT DOWN.
18 900922 F
0.0 H
4 N/A HH -
PUMPXX "2C" CONDENSATE PUMP'TAKEN OUT 0F SERVICE FOR PUMP PACKING PR06LEMS.
193.6 (1)
(2)
(3)
(4)
F - FORCED REASON METH00 EXHIBIT.G -~lNSTRUCTIONS 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 (NUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER(EXPLAIN)
-EXHIBIT I - SAME SOURCE
~
i r
UNIT SHUTDOWNS AND POWER REDutil0NS DOCKET no. 50 - 278-UNIT 1AME PEACH BOTTOM UNIT 3,
DAti OCfosER' 15,~1990'
~
REPORT MONTH SEPTEMBER, 1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY
. M. J. BARON.
1 SUPERVISOR REPORTS CROUP.
(
! PEACH BOTTOM ATOMIC POWER STATION =
{
TELEPHONE (717) 456-7014 EXT. 3321 i
METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING S0WN EVENT CODE
- iCODE,
-ACTION TO' NO.
-DATE (1)
(HOURS)
(2)
REACTOR (3)
REPORT #-
'(4) 1 (5)
PREVENT RECURRENCE i
~
t 14 900906 5
0.0 N
4 N/A HC HTEXCH "Al" WATERBOX INSPECil0N.
REACTOR WAS NOT SHUT L'WN.
15 900907
.S 0.0 H
4 N/A HC HTEXCH "A2" WATERBOX INSPECTION.
REACTOR WAS NOT. SHUT DOWN.
.. 5 2
16 900910 F
0.0 N
.4 N/A HH 222222 POWER REDUCil0N DUE TO HIGH COPPER CONTENT.IN THE CONDENSATE.
REACTOR WAS NOT $ NUT DOWN.-
A
=
(1)
(2)
(3)
('4) i F - FORCED REASON METHOD EXHIBli C - INSTRUCTIONS
$ - 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) s 0 - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE (NUREG-0161)-
E - OPERATOR TRAINING + LICENSE EXAMINAfl0N F - ADMINISTRATIVE.
G - OPERATIONAL ERROR (EXPLAIN)
..(5)~
H - OTHER(EXPLAIN)
EXHIBIT I - SAME SOURCE, 1
l l
l i
I
'