ML20044B336
| ML20044B336 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/30/1990 |
| From: | Baron M, Miller D PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CCN-90-14135, NUDOCS 9007180358 | |
| Download: ML20044B336 (14) | |
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CCN-90-14135:
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~l PHILADELPHIA ELECTRIC COMPANY ;
l- PIACilIK1TIDM AlDMIC POTER STATION i R. D. I, llox 208 i Delta, Itnrnylvania 17314 l pasas eurmes ress ponim oe tutttawa pl?) 4567014 1 D. a. MDier. Jr. July 16, 1990
, Vice Pres 6 dent Docket Nos. 50-277 50 278 j I
U.S. Nuclear Regulatory Commission i p- Document Control Desk l Washington, DC 20555 i
SUBJECT:
Peach Bottom Atomic Power Station Monthly Operating Report i Gentlemen: j l
Enclosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and i 3 for the month of June 1990 forwarded pursuant to Technical Specification 6.9.1.d under the I guidance of Regulatory Guide 10.1, Revision 4. A correction to the May,1990 Unit Shutdowns and i Power Reductions is also included.
i Sincerely, l 9 )
f[f lAJ1 V DBM/AAF/MJB: cmc Enclosure :
cc: R.A. Burricelli, Public Service Electric & Gas T.M. Gerusky, Commonwealth of Pennsylvania i JJ. Lyash, USNRC Senior Resident Inspector ,
R. McLean, State of Maryland i T.T. Martin, Administrator, Region I, USNRC ,
H.C. Schwemm, Atlantic Electnc J. Urban, Delmarva Power i t INPO Records Center L :
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CCIl690.NRC
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V 900718C358 900630 PDR R ADOCri 05000277 I PDC
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NRC Monthly Operations Summary Peach Bottom Atomic Power Station June 1990 ;
l UNIT 2 , l l
Unit 2 began the month at 100% power. On June 11, two sensing lines to a 'B' RHR flow clement were found to have been reversed during recent rework. The related instrumentation was for Containment Spray. Decause i of this, a Limiting Condition for loss of Containment Spray was entered. Repairs were made and the limiting )
J condition was ekmed out.
On June 18, severe thunderstorm activity caused the static inverter to swap to the alternate power r.ource. This caused the recire MG set to initiate a runback of the recire pumps to 60% speed.
The RWCU was shut down on June 19 for maintenance to the MO-18 outboard suction isolation vahc, which had a significant packing leak. RWOU was returned to service, but during startup and restoration, RWCU i isolated due to high flow. The isolation was reset without incident, and a 4 hout notification was made to the 1 NRC, j j
The Unit reduced power to 80% on June 22 because of copper levels above 0.3 ppb Copper levels dropped and l on Ju.se 24, power increases were started. The unit reached 100% power on June 25.
On June 30, a rod pattern adjustment was made, and the unit fmished the month at 90% power.
UNIT 3 ]
On June 1, the unk was at 91% power because of problems with the 3 'C' circ water pump, and degrading i condenscr efficiency caused by rising river water temperatures. On June 3, a load reduction was begun to I support bushing repair on the 3 *B' recite MG set transformer. The brushes were also replaced. Investigation 1 indicated that the 3 'A' MG set needed brush repair also. 3 'B' was returned ta senices on June 5, and 3 'A' l was removed from service on June 6. Repairs were made, and the 3 'A' recire pump was restarted. The 3 *C" I circ pump was also returned to e,cnice, and the unit increased power, reaching 100% on June 10.
On June 16, the 3 'A' condensate pump tripped on instantaneous overcurrent. The recite pumps ran back to 60% speed as designed. A faulty cable on the 'A' phase was replaced. Power was returned to 100% by June 19.
The RWCU system was shut down on June 20, for maintenance to the packing of the MO 18 outboard suction isolation valve. After investigation it was determined that packing repairs were not needed. RWCU was returned to service, but during startup and te storation, RWCU isolated due to high flow. The isolation was reset J without incident, and a 4 hout notification was made to the NRC.
An EHC leak on the #3 control valve for the main turbine was discovered on June 24. Power was reduced to allow for inspection of the leak. Power was reduced again on June 25 so that the turbine could be tripped and -
the leak repaired. Repairs were comple'.ed and the generator was again synchronized to the grid. The unit was at 100% by Jur.c 29.
C00690SRC l
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AvtRAGE DAILY UN11 POWER Livil 000 Kit NO. 50 - 217
(*1T PEACH B0ff0M Uhtt !
DATE JULY 15, 1990 COMPANY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERYl50R REPOR11 GROUP PtACH BOTTOM ATOMIC POWER STA110N TELEPHDat (717) 45tr-7014 EKf. 3321 MONTH JUNE 1990 DAY AvtRAGE DAILY POWER LEVtt DAY AVERAGE DAILY POWER LEVEL (Wi-NET) (MWi-Nii) 1 1060 17 1057 2 1054 18 1045 3 1060 19 1041 4 1061 20 1058 5 1065 21 1043 6 1061 ft 966 7 1058 23 751 8 1064 24 982 9 1063 25 1037 10 1056 26 1043 11 1054 27 1042 12 1054 70 1048 13 1053 29 1040 14 1062 30 814 15 1056 16 1054
%'
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- e AVERAGE DAltY UNIT POWER Livil l
DOCK [i NO. 50 - 278 Wii P[ACH BOTTOM UNil 3 DAT( JULY 15, 1990 COMPANY PHILADELPHIA (LECTRIC COMPANY M. J. 6 ARON
$UPIRV150R RtPORT5 GROUP P[ACH BOTTON ATOMit POW P 3 TAT 10N tittPHONE (717) 456-7014 EK1. 4321 MONTH JUNE 1990 DAY AVikAGE DAILY POWER LtVEL DAY AVERAGE DAILY POWER LEWLL (MWE-NET) (MWE-NCT) 1 940 17 840 t 916 18 896 3 789 19 1032 4 386 20 1048 5 472 21 1038 b 619 !! 1041 7 8/9 23 1043 8 966 24 1046 9 993 25 54 5 10 1051 26 157 11 1053 27 619 12 1048 28 988 13 1048 29 1039 14 10$$ 30 1039 15 1055 16 940
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L Docket No. .S277 Attachment to Monthly Operating Report for June 1990 Page 2 UNIT 2 REITELING INFORMATION (Continued)
- 8. The pecaent licensed spent fuel pool storage capacity and the slic of any Lscrease in licensed storage capacity that has been requested or is planned,la number of fuel auemblies:
The spent fuel pool storage capacity has been reticensed for 3819 fuct aucmblics.
- 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity:
Septemter 2003 without full core offload capability.
Septemter 1997 with full core offload capability.
C NA0.NRC
Docket No. 50 277 Attachment to Monthly Operating Report for June 1990 UNIT 2 REIVELING 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 license amendment?
Yes, 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:
To be determined.
- 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 assemblics (a) in the core and (b) in the spent fuel storage pool:
. (a) Core 764 Fuel Assemblics (b) Fuct Pool .1734 Fuel Asr.cmblics,58 Fuct Rods CCh90.NRC
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Docket No. 50-278 Attachment to Monthly Operating Report for June 1990 Page 2 UNIT) REITELING INFORMATION (Continued)
- 8. The present licensed spent fuel pool storage capacity and the sire of any increase in licensed storage capacity that has been requested or is planned, in admber of fuel assemblies:
The spent fuel pont storage capacity has been relicensed for 3819 fuel assemblics. Modification of the fuel pool is expeded to be cunplete 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 reracking modification):
September 1996 without full core offload capability.
End of next cycle with full core ofiload capability (est. January 1991).
With increased fuct pool capacity (subsequent to the completion of the fuel pool rcracking modification):
September 2004 wahout full core offload capability.
September 1998 with full core offload capability.
CCD690.NRC
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l' Docket No. 50-278 Attachment to -i Monthly Operating i Report for June 1990 ;
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UNIT 3 REFUELING INFORMATION ;
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- 1. Name of facility: ;
Peach Bottom Unit 3
- 2. Scheduled date for next refueling shutdown: f Reload 8 scheduled for August 31,1991
- 3. Scheduled date for restart following refueling Restart following refueling scheduled for November 29,1991 i
- 4. Will refueling or resumption of operation thereafter require a technical specification change or other licenric amendment? ;
Yes.
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:
To be determined, i
l 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, {
l- unreviewed design or performance analysis methods, significant changes in fuel design, new operating l procedures:
L- 7. The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool-l 1
(a) Core 764 Fuel Assembbes (b) Fuel Fool 14% Fuel Assemblics,6 Fuel Rods t
l CCD690.NRC
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OPERATING DATA REPORT DOCKET NO. 50 - 277 Daft JULY 16, 1990 COMPLtit0 BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON
- $UPERV150R REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (117) 456-7014 EXT. 3321 OPERATING $1ATUS
- 1. UNIT NAMC: PEACH BOTTOM UNIT 2 NOTE $1
- 2. REPORilNG PIR100: JUNE. 1990
- 3. LICEN$tD THIRMAL PhtR(WI): 3293
- 4. NAMEPLATE RATING (GRO$$ MWE): 1152
- 5. DE$1GN [LECTRICAL RATING (NET WE): 1065
- 6. MAXIMUM DEPENDABLE C.',?ACITY (GROS $ MWE): 1098
- 7. MAXIMUM DIP [NDABLE CAPACITY (NET WE): 1055
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) $1NCE LAST REPORT. GIVE REASONS:
- 9. POWER LEVil TO WHICH R[$1RICilD. IF ANY (NET Nf):
- 10. RIA10NS FOR RESTRICTIONS. IF ANY THl$ MONTH YR-10-DATE CUMULATIVE
- 11. HOUR $ IN REPOR11NG PERIOD 720 4.343 140,159
- 12. NUMBER OF HOLR$ REACTOR WA$ CRITICAL 720.0 3.019.4 82.546.7
- 13. REACTOR RE$tRVE $HUTDOWN HOUR $ 0.0 0.0 0.0
- 14. HOUR $ GENERATOR ON-LINE 720.0 2.909.5 79.514.8
- 15. UNIT RESERVE $HUTDOWN HOUR $ 0.0 0.0 0.0
- 16. GROS $THIRMALENERGYGENERATED(MWH) 2.318.664 8.678.472 233.974.605
- 17. GROS $ELECTRICALENERGYGENERATED(MWH) 769.900 2.861.900 76.921.790 18.NETELECTRICALENERGYGENERATED(MWH) 742.399 2.757.687 73.612.536 PAGE 1 0F 2
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OP[RATINGDATAREPORT(CONilNut0) 00CKti NO. 50 - 277 L Daft JULY 15, 1990 THi$ MONTH YR-10-Daft CUMULAi]VI
- 19. UN!i SERVICE FACTOR 100.0 C7.0 $6.7
, 20. UNIT AVAILABILITY FACTOR 100.0 67.0 $6.7 21.UhliCAPACITYFACTOR(U$1NGMDCNti) 97.7 60.2 49.8
!!.UNITCAPACITYFACTOR(USINGDERNET) 96.8 59.6 49.3
- 23. UNIT FORCt0 OUTAGI Raft 0.0 20.2 14.7'
- 24. $HUTDOWS SCHEDUltD OvtR NtKi 6 MONTH $ (TYPC, DATE, AND DURATION OF (ACH):
!$. IF $HUTDOWN AT [ND OF REPORT PERIOD, [$f!MAi[D DATE OF $1ARTUP:
26.UNii$INTESTSTATUS(PRIORTOCOMMERCIALOPERAll0N): FORECA$i ACHIEVCD INiilAL CRiflCAllif 09/16/73 INITIAL CLECTRICITY 02/18/74 COMMERCIAL OPERATION 07/05/74 PAGE 2 0F 2 i
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OPERATING DATA REPORT DOCKET NO. 50 - 278 DATE JULY 15, 1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON
$UPERVISOR REPORTS GROUP PEACH BOTTON ATOMIC POWER $TATION TELEPHONE (117) 456-7014 EXT. 3321 OPERATING STATUS
- 1. UNIT NAME: PEACH BOTTOM UNIT 3 NOTES:
- 2. REPORTING PERIOD: JUNE, 1990
- 3. LICENSED THERMAL POWER (WT): 3293
- 4. NAMEPLATE RATING (GROS $ WE): !!$2
- 5. DESIGN ELECTRICAL RATING (NET WE): 1065 i
- 6. MAXIMUM DEPENDABLE CAPACITY (GROS $ WE): 1098 t
- 7. MAXIMUM DEPENDABLE CAPACITY (h(T WE): 1035
- 8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) $1NCE LAST REPORT, GivE REA$0N$:
- 9. POWER LEVEL TO WHICH RE$iRICTED, IF ANY (NET WE):
- 10. REASONS FOR RESTRICT 10N$, IF ANY:
THl$ MONTH YR-TO-DATE CUMULATIVE
- 11. HOUR $ IN REPORTING PERIOD 720 4.343 136,055 12, NUMBER OF HOUR $ REACTOR WAS CRITICAL 720.0 4,174.5 81,333.3 >
- 13. REACTOR RE$ERVE SHUTOOWN HOUR $ 0.0 0.0 0.0
- 14. HOUR $ GENERATOR ON-LINE 714.3 4.101.1 78,503.3 15, UNIT RESERVE SHUTOOWN HOUR $ 0.0 0.0 0.0
- 16. GROS $ THERMAL ENERGY GENERATED (WH) 2,035,920 12,542,501 228.705,370 I
- 17. GROS $ ELECTRICAL ENERGY GENERATED (WH) 663,800 4,144,600 75,016,732 18.NETELECTRICALENERGYGENERATED(MWH) 638,118 4.011.018 71,853,586 FAGE 1 0F 2 l
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DP[RAi!NG DATA REPDR1 (CDNilNU[D) DDCKET ND. $D - !?S '
DATE JULY 15. 1990 THl$ MDNTH YR-TD-DATE CONJLAi!YE
- 19. UNIT $[RVICE FACfDR 99.2 94.4 $7.7
- 20. UNIT AVAILABILITY FACTOR 99.2 94.4 $7.7
!!. UNIT CAPAtlTY FACfDR (U$1NG MDC NET) 85.6 89.2 51.0
- 22. UNii CAPAtlfi FACTDR (USING DER NET) 83.2 86.7 49.6
- 23. DNIT FDRCED DUTAGE RATE D.8 5.6 !!.9
- 24. $HUTDDWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE. DATE. AND DURATIDN DF [ACH):
MID-CYCLE MAINT[ NANCE DUTAGE STARTING DCfDBER 27 SCHEDULED FDR !! DAYS.
- 25. IF $HUTDDWN AT [ND DF RIPDRi PERIDD. ($11 Mall 0 DATE OF STARTUP:
- 26. UNif$ IN TEST STATUS (PRIDR 10 CDMMERCIAL DPERATIDN): FDRECAST ACHitVED !
Ih!T!AL CR!ilCALITY D8/07/74 INITIAL [LECTRICITY D9/01/74 CDMMERCI AL DP[RATIDN !!/23/74 PAGE 2 DF ! l
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UNIT $HUTDOWNS AND POWER REDUCT!ONS C TKti NO. 50 - 277 UNIT NAME PEACH bOTTON UNIT t DATC JULY ll, 1990 REPORT MONTH JUNE, 1990 COMPLETED BY PHILADELPHIA [L[CTRIC COMPANT M. J. BARON
$UPERVl$0R REPOR1$ GROUP PEACH BOTTOM ATOMit POWER $1ATION T[LLPHONE (117) 456-7014 EXT. 3321 METHOD OF LICEN$lt $YST[M COMPONENT CAU$( AND CORRECTIV[
TYP[ DURATION REA$0N $HU111NG DOWN [ VENT CODE CODE ACT10N TO NO. DATE (1) (HOUR $) (t) REACTOR (3) REPORT f (4) ($) PR[ VENT RECURRENCC 9 000622 F 0.0 H 4 N/A HH ZZZZZZ POWER REDUCTION DUt 10 HIGH COPP[R CONI [Ni IN THE CONDENSATE. REACTOR WA$ N01 $ HUT DOWN.
10 900029 $ 0.0 H 4 N/A RB CONR00 10 $[T FULL POWER ROD PATT[RN CH PUMPXX FB FEED PUMP COUPLING MAINT.
HH PUMPXX 2C CONDENSATE PUMP TAK(N OFF FOR TBCCW LEAK HH PUMPXX 2B CONDth$ ATE PUMP P.M.
(1) (t) (3) (4)
F - FORCED REASON METHOD EXHlBli 0 - IN$1RUCT10NS
$ - SCHEDUlt0 A - EQUl? TNT FAILURE ([XPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MM NT[ NANCE OR Tisi ! - MANUAL $ CRAM. ENTRY $HIETS FOR LICENSEE C 'aEFUELING 3 - AUTOMATIC $ CRAM.
D - REGULATORY RESTRICTION 4-OTHER([XPLAIN) EVENTREPORT(LER))
FlLE (NUR[Cr4161 1 - OP[RATOR TRAINING + LIC(N$t EXAMINATION I - ADMINISTRA11VE ($)
i.-OPERA 110NAL[RROR([XPLAIN) o - OTHER(tXPLAIN) EXHlBli ! - SAME SOURCE 1
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE JULY 15, 1900 REPORT MONTH JUNE,1990 COMPLETED BY PHILADELPH A ELECTRIC COMPANY M. J. BARON
' SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717)456-7014 EXT.3321
SYSTEM COMPONENT CAUSE AND CORRECTIVE METHOD OF LICENSEE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO
- NO. DATE (1) (HOURS) (2) REACTOR (3) REPORT f (4) (5) PREVENT RECURRENCE
?? 900603 F 0.0 A 4 N/A CB TRANSF "B" RECIRC M/G SET TRANSFORMER O!L LEAK. REACTOR WAS NOT SHUT DOWN.
B 900616 F 0.0 A 4 W!n HH .PUMPXX 3A CONDENSATE PUMP TRIP DUE T0 INSTRUMENT OVERCURRENT.
REACTOR WAS NOT-SHUT 00WN.'
9 900624- F . 5.7 H 4 N/A HA TUR8IN UNIT 3 TURBINE TRIP FDR REPA!R OF THE #3 CONTROL VALVE.
n REACTOR WAS NOT SHUT 00WN.
1 5.7 ,
(1)l (2) (3) (4)
F - FORCED- REASON. METHOD EXHIBli 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 - REFDELING . 3 - AUTDMATIC SCRAM. EVENT REPORT (LER) 0 - 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 8
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L Co rection to previously submitted report:
UNIT SHUTDOWNS AND POWER REDUCTIDNS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE JUNE 15, 1990 REPORT MONTH- MAT. 1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717)456-7014 EXT.'3321 METHOD OF LICENSEE STSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT- CODE CODE ACT!0N TO NO. DATE (1) (HOURS) (2) REACTOR (3) REPORT f- (4) (5) . PREVENT RECURRENCE 1
5 900501 A 0.0 : H 4 N/A WH HNM POWER REDUCTION DUE TO DEGRADED CONDENSER HF PUMPXX PERFORMANCE. C CIRC WATER PUMP OUT OF.
B SERVICE REACTOR WAS NOT SHUT DOWN.
'6 900516 F 0.0 A 4 N/A CB PUMPXX "A" RECIRC PUMP TRIP DURING A BRUSH REPLACEMENT. REACTOR WAS NOT SHUT DOWN.
(1) (2) (3) (4)
F - F - FORCED' REASON METH00 EXHIBIT 6 - 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 - AUT0NATIC SCRAM. EVENTREPORT(LER):
0 - REGULATORY RESTRICTION 4-OTHER(EXPLAIN) FILE (NUREG-0161)'
E - OPERATOR TRAINING + LICENSE EXAMINATION r - ADMINISTRATIVE-- ' (5) 6 - OPERATIONAL ERROR (EXPLAIN)
H - OTHER(EXPLAIN) EXHIBli 1 - SAME SOURCE f
. . . . . _