ML20034A850
| ML20034A850 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/31/1990 |
| From: | Baron M, Danni Smith PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9004240433 | |
| Download: ML20034A850 (14) | |
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-CCN-90-14062?
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PHILADELPHIA' ELECTRIC COMPANY PEACH BCTI'1DM ATOMIC POWER STATION '-
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- R. D.1 Box 208 -
Delta. Pennsyh ania 17314 PEACH portOM-THE POW'ER OF EXCELLENcr (717)456-7014 D. M. Smith April 12,.1990
. Docket Nos. ' 50-277 50-278 LU.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 March 1990 forwarded pursuant to Techmcal Specification 6.9.1.d under the -
l guidance of Regulatory Guide 10.1, Revision 4.
- Sincerely, r
DMS/TEC/MJB: cmc Enclosure cc:
R.A. Burricelli, Public Service Electric & Gas l
T.M. Gerusky, Commonwealth of Pennsylvania l
J.J. Lyash, USNRC Senior Resident Inspector T.E. Magette, State of Maryland l
T.T. Martin, Administrator,- Region I, USNRC l
H.C. Schwemm, Atlantic Electric J. Urban, Delmarva Power INPO Records Center 1.
CC0390.NRC 9004240433 900331 PDR ADOCK 05000277 R
PDC p
NRC Monthly Operations Summary Peach Ilottom Atomic Power Station March 1990 4
UNIT 2 The unit began the month at 73% power with preparations for shutdown in progress. The mode switch was.
i placed in shutdown for the scheduled mid cycle maintenance outage on March 2.
The Safety Systems Functional Inspection exit meeting was held on March 8. The most serious area of concern was that the operability of the Emergency Service Water System had not been demonstrated. Justification for continued operation of unit 3 only was made and diagnostic testing was started.
Mid cycle outage activities were completed on March 19. The unit remained shut down for the rest of the month for Emergency Service Water System flow testing and cleaning.
UNIT 3 The nr.it bcgan the month at 100% power. On March 6, the unit experienced a turbine trip and reactor scram.
The turbine trip was caused by the trip of the stator cooling water pump which occurred while the second stator cooling water p;mp was blocked for maintenance. Forced outage maintenance activities were performed but startup was delayed pending resolution of a Justification for Interim Operation related to environmental qualification of certain HPCI components.
On March 10, after the concerns were resolved, the unit was placed in startup. The generator was synchronized to the grid on March 11. Power was increased to nomina 190% by March 15 but was reduced to 62% for control rod pattern adjustment and minor maintenance work.
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The unit reached 100% power on March 17 and remained at that level urts March 24 when power was reduced to repair a feedwater heater drain valve. The valve was repaired and power was returned to 100% on March.
- 25. The unit remained at 100% for the rest of the month.
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CC0390.NRC i
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,y Docket No.'50-277
- Attachment to Monthly Operating Report for March 1990 I
UNIT 2 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 2 2.
Scheduled date for next refueling shutdown:
Reload 8 scheduled for January 6,1991 3.
Scheduled date for restart following refueling:
Restart following refueling scheduled for April 5,1991 4.
Will refueling or resumption of operation therefore require a technical specification change or other
- i license amendment?
Yes.
l If answer is yes, what, in general, will these be?
Reload amendments for cycle 8.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
j To be determined.
s 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 in order for PECo to do reload licensing analyses in-house for Unit 2 Cycle 9, NRC approval i
of one report (PECO-FMS-006) must be obtained by May 31,1990. This report is the last in I
a series of six reports to demonstrate PECo's ability to perform the analyses. The report has been submitted and is scheduled for completion in May 1990.
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7.
The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:
(a)
Core - 764 Fuel Assemblies (b)
Fuel Pool 1734 Fuel Assemblies,58 Fuel Rods Docket No. 50-277 t
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CC0390.NRC
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t Attachment to Monthly Operating Report for March 1990 Page 2 i
UNIT 2 REFUELING INFORMATION (Continued) -
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8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage 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 assemblies.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the,
t present capacity:
September 2003 without full core offload capability.
September 1997 with full core offload capability.
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Docket No. 50-278 Attachment to Monthly Operating Report for March 1990 UNIT 3 REFUELING INFORMATION 1.
Name of facility:
. Poach BONom Unit 3 2.
Scheduled date for next refueling shutdown:
Reload 8 scheduled for August 31,1991 4
Scheduled date for restart following refueling Restart following refueling scheduled for October 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 te?
Reload amendments for cycle 8.
5.
Schedcled date(s) for suluuining proposed licensing action and supporting information:
To be determined.
6.
Important liccasing considerations associated with refueling, e.g., new or differem fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
In order for PECo to do reload licensing analyses in house for Unit 3 Cycle 9, NRC approval of one report (PECO FMS 006) must be obtained by May 31,1990. This seport is the last in a series of six reports to demonstrate PECo's ability to perform the anel:ses. The report has been submitted and is scheduled for completion in May 1993.
7, The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a)
Core 764 Fuel Assemblics (b)
Fuel Pool 1496 Fuct Assemblics,6 Fuel Rods CCO.190,NRC l
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Docket No..%278 Attachment to Monthly Operating Report for March 1990 Page 2
,M[T 3 REFUELING INFORM ATION (Continued) 8.
The present licensed spent fuel pool s.torage capacity and the size of any increase in licensed storage capacity that has been requested or is planned,in numter of fuct assemblies:
The spent fuel pool storkge capacity has been relicensed for 3819 fuel assemblics. Modification of the fuel pool is expected to te complete in the fourth quarter of 1990.
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 19(X, without full core ofiload capability.
End of next cycle with full core offload capability (est. January 1991).
With increased fuel pool capacity (subsequent to the complction of the fuel pool rcracking modification):
September 2004 without full core offload capability.
September 1998 with full core offload capability.
CGD90.NRC i
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xy AVERAGE DAILY UNIT PMR LEVEL -
- 00CKti NO. $0 - 277' UNIT PEACH DOT 10M UN!1 2 DATE APRit 15. 1990 COMPANY PHILADELPHIA ELECTRIC COMPANY M."J. BARON
$UPERVISOR RtPORTS GROUP ~--
PtACH BOTTOM ATOMIC PMR $1ATION -
. TELEPHONE (717)456-7014 EXT.3371 MONTH MARCH 1990' OAY -' AVERAGE OAILY POWLR Livil DAY 'AV[ RAGE DAILY POWR LEVEL (MWC-Nti)
(NWC-Nti)-
1 747 17 0
t 633 10 0-3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
23' 0
8 0
to 0
9 0
tb 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30
.0 15 0
31 0
16 0
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AV(RAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 278 -
UNIT PEACH BOTTOM UNIT 3 ~
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Daft APRIL 15. 1990.
COMPANY PHILA0(LPHIA [LLCTRIC COMPANY M. J. BARON '
$UPERVISOR R[ PORTS GROUP' PEACH BOTTOM ATOMIC POWER STATION.
T(L(PHONE (717)456-7014 EXT.'3321 MONTH-MARCH 1990 DAY AV[ RAGE DAILY POWER LEVEL
DAY AVIRAGE DAILY POWER LEVEL' (MWE-NET)
(NWE-NET) 1 1070 17 1035.
2 1070 18 1063-3 1058' 19
'1063-4 1071 20 1071 5
1068 1058 6
118 1062.
7 0
23-
- 1070-8 0
24 1013 9
0-25 1054-10 0
26
'1066 11 1
27 1066
' It '
512 28 1071' 13.
848 29 1066 14 939 30 1066-15 914 31 1070:
'16 864
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1 OPERATING DATA REPORT-DOCKET NO 50 - 277-
.DATE APRll' 15;1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT, 3321 OPERATING STATUS
- 1. UNIT NAME: PEACH BOTTOM UNIT 2 NOTES:
2 RfPORTING PERIOD:
MARCH, 1990-UNIT WAS SHUT DOWN TWOUGH MOST'0F
- 3. LICENS&D THERMAL POWER (MWT) -
3293 MARCH FOR SCHEDULED MID-CYCLE >
'4.NAMEPLATERATING(GROS $MWE):
1152 MAINTENANCE OUTAGE. THE UNIT
- 5. DE$1GN ELECTRICAL RATING (NET MWE):
1005' REMAINED $ HUT 00W AFTER OUTAGE
- 6. MAXIMUM DEPENDABLE CAPACITY-(GROS $ MWE): 1098 --
ACTIVlflES WERE COMPLETED FOR -
7.MAXIMUMDEPENDABLECAPACITY(NETMWE):
1055' EMERGENCY $ERVICE WATER FLOW TESTING.
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) $1NCE LAST REPORT, GIVE REA$0NS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE)t
- 10. REASONS FOR F.[$TRICT10N$r IF ANY:
THl$ MONTH YR-10-0 ATE CUMULATIVE.
- 11. HOUR $ IN REPORTING PER100 744 2,160 137,976
- 12. NUMBER OF HOUR $ REACTOR WAS CRITICAL
- 45.4 -
1,416.8
.80,944.1
- 13. REACTOR RE$[RVE SHUT 00WN HOUR $
0.0 0.0 0.0
- 14. HOUR $ GENERATOR DN-LINE 45.4 1.398.6-78.003.9
- 15. UNIT RESERVE $ HUT 00WN HOUR $
0.0 0.0
-0.0-
- 16. GRD$$ THERMAL ENERGY GENERATED (MWH) 104.112
-3,977,064" 229,273,257' 17.GRO$$ELECTRICALENERGYGENERATED(MWH) 34,200 1,308,400 75,368,290'
- 18. NET [LECTRICAL ENERGY GENERATED IMWH) 28,843 1,265,134' 72,119,983-PAGE 1 0F 2 1
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n OPERATING DATA REPORT (CONTINUED)
. DOCKET NO. 50 - 277 DATE APRIL 15. 1990
-i THis MONTH YR-TO-DATE Ctt:ULATIVE
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- 19. UNIT SERVICE FACTOR 6.1 64.7
$6.5 -
- 20. UNIT AVAILABILITY FACTOR 6.1
'64.7 56.5
.21.UNITCAPACITYFACTOR(U$1NGMDCNET) 3.7 55.5
-49.6 22.UNITCAPACITYFACTOR(U$1NGDERNET) 3.6 -
$$.0 49.1
- 23. UNIT FORCED OUTAGE RATE -
0.0 '
4.3 14.3
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- 24. $HUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):
2$. If SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:
PENDING ESW FLOW TEST RESULTS.
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- 26. UNITS IN TEST $1ATUS (PRIOR TO COMMERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 lq INITIAL ELECTRICITY 02/18/74.
l COMMERCIAL OPERATION 07/05/74
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' OPERATING DATA REPORT-
!j 00CKET No. 50 - 278 -
DATE APRIL 15, 1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON'
-SUPERVISOR
.l REPORTS GROUP-TELEPHONE (117) 456-7014 EXT. 3321 '
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. PEACH BOTTOM ATOMIC POWER STATION.
OPERATING STATUS
- 1. UNIT NAME: PEACH 8OTTOM UNIT 3 NOTES:
- 2. REPORTING PER100:
MARCH 1 990 3.LICENSEDTHERMALPOWER(MWT):
3293
[
4.NAMEPLATERATING(GROSSMWE):
11$2
$. DESIGN ELECTRICAL RATING.(NET MWE):
1065 6.MAXIMUMDEPENDA8LECAPACITY(GROSSMWE): 1098
- 7. MAXIMUM DEPENDA8LE CAPACITY (NET MWE): '1035
- 6. IF CHANGES OCCUR IN CAPACITY RATlhGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT,' GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTEO, if ANY (NET MWE):
- 10. REASONS FOR RESTRICT 10NS, IF ANY:
THIS MONTH YR-TO-DATE
-CUMULATIVE-11, HOURS IN REPORTING PERIOD 744 2,160 133,872
- 12. NUMBER OF HOURS REACTCA WAS CRITICAL 636.2 1,991'6-79,250.3
- 13. REACTOR RESERVE SHUT 00VN HOURS
' O.0
' O.0 0.0
- 14. HOURS GENERATOR ON-LINE-605.3-1,923.8' 76,326.0'
- 15. UNIT RESERVE $:tVT00WN HOURS 0.0 0.0 0.0 16.GROSSTHERMALENERGYGENERATED(MWH) 1,886,309 6,039.509; 222,202,378 17.GROSSELECTRICALENERGYGENERATED(MWh) 629,000
-2,008.100 72,880,232
- 18. NET ELECTRICAL ENERGT GENERATED (MWH):
609,287 1,950,510 69,793,078
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OPERATINGDATAREPORT(CONTINUED)
DOCKET NO. 50 - 278' DATE APRll 15, 1990 THl$ MONTH YR-T W TE CUMJLATIVE-
- 19. UNIT $[RVIC[ FACTOR 81.4 -
89.1
$7.0
- 20. UNIT AVAILABILITY FACTOR 81.4
.89.1
$7.0
= 21.UNITCAPACITYFACTOR(U$1N6MDCNET)
.79.1 87.2
- $0.4 '
22.UNITCAPACITYFACTOR(USINGDERNET) 76.9 84.8 49.0
. 23. UNIT FORCED OUTAGE RATE
- 18. 6. '
10.9 13.2 -
- 24. $HUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF [ACH):
' MID CYCLE MAINTENANCE OUTAGE, 21 DAY DURATION, STARTING 10/27/90.
- 25. 1F SHUTDOWN AT END OF R[ PORT PCR100, ESTIMAftD DATE OF STARTUP:
$1
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERAT!DN):
FORECAST ACH1[VED INITIAL CRIflCALITY 08/07/74 INITIAL [LECTRICITY 09/01/74:
COMMERCIAL OPERAT!DN 12/23/74 PAGE 2 0F.2 1
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UNIT $HUTDOWN$ AND POWER REDUCTIONS DOCKET NO. $0 - 277 UNIT NAME PEACH BOTTOM UNIT 2' DATE APRIL 16, 1990
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REPORT MONTH MARCH, 1990
-COMPLETED BY PHILADELPHIA ELECTRIC COMPANY
.M. J. BARON
$UPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATiDN TELEPHONE (717) 45Er-7014 EXTi 3321 METHOD OF LICENSEE SYSTEM COMPONENT CAU$E AND CORRECTIVE TYPE DURATION REASON $ HUTTING 00WN EVENT CODE CODE ACTION TO NO.
DATE (1)
(HOURS)
- (2)
REACTOR (3)
REPORT f (4)
($)
PREVENT RECURRENLE~
900302
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1 N/A XX XXXXXX MID-CYCLE OUTAGE.
(1)
(2)
(3)
(4).
F - FORCED REASON METHOD EXHIBli G - INSTRUCTIONS
$ - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY $HEET$ FOR LICENSEE C - REFUEllNS 3 - AUTOMATIC $ CRAM.
EVENTREPORT(LER))-
0 - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE (NUREG-0161 E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE
($)
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER(EXPLAIN)
' EXHIBli ! - $AME SOURCE l
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UNIT SHUTDOWN $ AND POWER REDUCTIONS DOCKET NO.' 50 - 2/8 UNIT NAME PEACH BOTTOM UNIT 3 -
DATE APRIL 16,1990-REPORT MONTH; MARCH, 1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY -
M. J. BARON
$UPERVI$0R REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT, 3321 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.
DATE (1)
(HOURS)
(2)
REACTOR (3)
REPORT f (4)
(5)
PREVENT RECURRENCE.
2 900306 F
138.7 A
3 3-90-03 CH
- PUMPXX, STATOR'C00 LING PUMP TRIP CAUSING' TURBINE TRIP AND RX AUTD-$ CRAM
~
3 900316 1.2 H
4 N/A RB CONP0D FINAL ROD PATTERN ADJUSTMENT REACTOR WA$ NF- $ HUT DOWN 4
900324 F
0.0 A
4 N/A CH VALVXX A3 FEEDWATER HEATER ISOLATION REClRC RUNBACK PER 01-104 REACTOR WAS NOT $ HUT DOWN 139.9 (1)
(2)
(3)
(4)
F - FORCED REASON METHOD EXHlBli G - INSTRUCTIONS
$ - SCHEDULED A - EQUlPMENT FAILURE (EXPLAlk) 1 - MANUAL
-FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY $HEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC $ CRAM.
EVENTREPORT(LER)
D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN).
FILC (NUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G-OPERATIONALERROR(EXPLAIN)
H-OTHER(EXFLAIN)
EXHIBIT I - SAME $0VRCE'
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