ML20077Q246

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Monthly Operating Repts for Jul 1991 for Peach Bottom Atomic Power Station Units 2 & 3
ML20077Q246
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 07/31/1991
From: Baron M, Miller D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CCN-91-14125, NUDOCS 9108210135
Download: ML20077Q246 (14)
v • d • e


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CCN 91-1412$

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August 15, 1991 Docket Nos. 50 277 ,

50 278  ;

U.S. Nudear Regulatory Commission Document Control Desk Washington, DC 20555 SUl1JECD Peach llottom Atomic Power Station Monthly operating Report Gentlemen:

Enclosed are twelve copies of the morahly operating report for Peach llottom Units 2 and 3 for the month of July 1991 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of if egulatory Guide 10.1, Revision 4.

Sincerely, /

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DBMLAAF/TJ /DRM/MJB: cmc b Enclosure ec: R.A. Ilurricelli, Public Service Electric & Gas T.M. Gerusky, Commonwealth of Pennsylvania J.J. Lyash, USNRC Senior Resident inspector R.I.- McLean, State of Maryland ,

T.T. Martin, Administrator Repion I. USNRC li,C. Schwemm, Atlantic Electric J, Urban, Delmarva Power INPO Records Center c(wll.yIK L .t u t,0 a

~ g 2q l 9108210135 910731 l ppR ADOCK 05000277 \

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. i NRC hionthly Operutions Summary Peach llottom Atomic Power Station '

July 1991 t

i l'Elll Unit 2 began the month with the rnode switch in 5t.irtup following the shutdown in June for repairs to a steam jet air ejector. The generator was synchrontied to the grid on July 1 and 1Rr;E power was reached on July 2. On  ;

July 3, power was reduced to N% after a trip of the *2N tecirc pump. The trip was related to the failure of a soldered splice on the field wiring of the associated htG set. Repairs were completed and 1[X)% power was reached on July 6. A 150 htWe load drop was taken on July 7 for a control rod pattern adjustment. On completion of the adjustments, power was returned to Im%. Unit power remained at the 1[X)% level for the rest of the month.

i I!Sil3 Unit 3 began the month at approximately 98% gmwer. The slight reduction in power was required to maintain i

adequate shutdown margin. An automatic scram occurred on July 7 when lightning r. truck the blockirig switch  !

on the generator output breaker. Lightning sirikes during the same storm also caused multiple grounds on the DC electrical rystem. Repairs were completed by July 14 and power ascension began but was held at approximately 75% to allow xenon to build and time for L.PRht gain calibration. Full power. approximately 97%

due to fuel depletion, was reached July 18 and remained there until a load drop to 7m blWe on July 21 for control eod pattern adjustment. Another load drop was taken on July 28 to valve out the extraction steam to the l

Sth stage feedwater heaters. Power was returned to approximately 98% anu remained at that level for the rest

  • of the month.

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Docket No. 50-277 Attachment to Monthly Operating i itcport for July IV>l I UNIT 2 Hl:FUlllNRINI'ORAliT11).S

1. Name of facility:

Peach Ilottom Unit 2

- 2. Scheduled date for next refueling shutdown:

Reload 9 scheduled for September 5,1992.

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3. Scheduled date for restart following refueling:

, Restart following refueling forecast for November 20,1V12, i

4. Will refueling or resurnption of operation therefore require a technical specification change or other I license amendinent? I No, if answer is yet,, what, in general, will these be?

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5. Scheduled date(s) for submitting proposed licensing action and supporting information: '

N/A

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 j procedures:

N/A t

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Docket No. $0 277 Attachment to Monthly Operating fleport for July 1911 Page 2

.Uh1LL10 i (TL131LLH11Mt GION (continued)

7. The number of fuel n'.semblies (a) in the core and (b) in the spent fur.1 storage pool:

(a) Core - 7M i uel Assemblics (b) Fuel Pool 1896 Fuel Assemblics, $8 ruct ihuls

8. The present licensed spent fuel pool storage capacity and the slic of any incicase in licer sed storage capacity that has been requested or is planned,in number of fuct assemblies:

The spent fuct p<xo storag capacity has been reticensed for M19 fuct assemblics.

9. The projected date of the last refueling that can be discharged to the spent fuel ;)ool assuming the present capacity:

September 2(KU without full core offload capability.

September 1937 with full core of00ad capability.

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Docket No. 50-278 Attachment to Monthly Operating Report for July 1931 UNIT 3 HIE 11LN11_lN1'OR%141RIS

1. Name of facility:

peach flottom Unit 3

2. Scheduled date for next refueling shutdown:

Reload 8 scheduled for September 14,1731

3. Scheduled date for restart following refueling Restart following refueling scheduled for December 7,19)1 4

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

See itern 6.

If answer is yes, what, in g-neral, will these be?

See item 6.

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

N/A 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analpis methods, significant changes in fuel design, new operating procedures:

Technical specification arocndment on reactor vessel pressure temperature limits prior to startup for cycle 9 was approved 6/27/91. (Technical Specification Change Request 90-17; 1

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Docket No. $0 278 i Attachment to i Monthly Operating Report for July 1991 Page 2  !

l UNIT 3 RITUEl ING INFORM ATION (Continued) t I

I 7 i The number of fuel anemblics (a) in the core and (b) in the spent fuel storage pool: l

)

(a) Core . 764 Fuct Aucmblies L

(b) Fuel Pool 1689 Fuel Aucmblies,6 Fuel Rods 8.

The prer.cnt licensed spent fuel pool storage capacity and the site of any increase in licensed r,toragj 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 second quarter of 1991.  !

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9. 6 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the i prCsent Capacity;

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With the current fuel peol capacity (prior to the completion of the fuel pool rcracking modification): k September 1996 without full core offload capability.

End of next cycle with full core offlod capability (est. January 1992). {

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With increased fuel pool capacity (subsequent to the completion of the fuel pool rcracking modificatio i September 2004 without full core offload capability.

t September 1998 with full core ofiload capability. {"

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. 4 AV(RAGE DAltY UNIT PDVER ((YtL DOCKlf NO. $0

  • 277 UNli PEACH B0110M UN!1 2 DATE AUGUST lb.1991 COMPANY PHILAD(LPHIA (LECTRIC CDMPANY M. J. BARON

$UPERVISOR REPDATS ONOUP PLACH B0110M ATOMIC POV(R $1Ai!ON lfLEPHONE (717) 456+7014 (XI. 3321 MONTH JULY 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVCRAG[ DAILY POVER ttVEL (MdE Nti) (FVt hET) 1 349 17 1040 2 1008 18 1043 3 998 19 - 1015 4 297 20 1028

$ 339 21 1023 6 879 22 1022 7 1030 23 1026 8 1040 24 1019 9 1041 25 1025 10 1040 26 1025 11 1040 21 1032 12 1043 28 1024 13 1043 29 1031 l 14 1036 30 1035 i 15 1047 31 1031 16 1034 o

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&OCKET NO. 50 - ??8 UNIT P[ACH B0110M UNIT 3 DATC AUGUST 15, 1991 COMPANY PH!LADELFHlA (L(CTRIC (OMPANY M. J. BARON

$UPIRylSOR REPOR1$ GROUP .I 1

FLACH BOTTOM ATOMIC POVER $iATION '

TILIPHONI (711) 456 7014 (XT, 3321 MONTH JUtY 1991 DAY AVERAGE DAILY POV(R LEV [L DAY AVERAGI DAILY POV[R L[ VEL (NE HIT) (MVI-NET) 1 1013 17 893 2 1014 18 1025 i 3 993 19 964 4 1004 20 981 5 999 21 BBS 6 999 22 1021 7 902 23 1013 8 0 24 1014 9 0 25 999 10 0 26 1012 11 0 21 1011 12 0 28 930 i ~I l

13 0 29 1015 2

14 48 30 1019 r

15 440 31 1011 1G 744 4

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  • E Or(RATING DATA REPORI I

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00CKti NO. 50 * !?? ,

DAll AUGUS1 15,199)

COMPLtit0 BY FHILADCLPHIA [LIC1RIC COMPANY

............................. ]

M. J. CARON i

SUPERVl10R '

REPDRi$ GROUP PIACH B0fiOM ATOMIC POWER STATION  !

TELEPHONC (117) 4561014 IXf. 3321 i OPIRATING $TATU$ '

......................................... j

1. UNIT NAME: PEACH B0if0M UN11 2 Nolts:

l F. RCPOR11NG PER100: JULY,1991

3. LICIN$to THERMAL POWER (Mii): 3293 '
4. NAMIPLATI RATING (GRO$$ MWI): j 1152

+

5. DE$10N (LECTRICAL RATING (Ntf MVC):

1065

6. MAXIMUM DIPENDABLE CAPACITY (GROS $ MWI): 1098
7. MAX! MUM DIPINDABLE CAPAtl1Y (NIT MWE):1055
8. IF CHANGl$ OCCUR IN CAPAC!f Y RAllNG1 (11tHS NUMBER 3 itA000H 7) $!NCC LAST REP t
9. PDVER Ltvil 10 VHICH Ri$TRICit0, IF ANT (Ntf MWI):
10. REASONS FOR RISTRICT10N$,1T ANY:

.i TH15 LONIH YR-TO-0 Aft CUMUL AI!VC

11. HOUR 5 IN RtPOR11NG PER100 744 5.087 149,063

!! NUMBER Of HOUR $ RIACTOR VA$ CRITICAL 744.0 2,782.7 88,983.4 r

13. RCACTOR RtstRVE SHUT 00VN HOUR $ 0.0 0.0 0.0
14. HOUR $ GENERATOR ON-LINE 739.3 F.098.3 85,683.4
15. UNIT RCSIRVE $Hu1DOWN HDURS t 0.0 0.0 0.0  !

............ . . . . . . . . . - . . ............ l

10. GROS $THIRMALINERGYGINERATED(MVH) 2.279.400 6.018,504 252.435,537

............ ............ i

17. GROSS (LECTR! CAL ENERGY GENERAtto (FVH) 742.700 1,939,200 82,947,490
16. NET CLECTRICAL ENERGY GENERATID (MJH) 712,4?9 1,844,373 79,399.019

............ ............ ............ {

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Ot!R A11NG DATA RtPOR1 (CONTINut0) D0C011 h3. 50 . ???

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THl$ MONTH YR 10-DATE CUHUL AtlVI i i

19. UNif SERVICC FACTOR 99.4 41.2 $1.3 ,
20. UNif AVhlLABIL11Y FAC10R 99.4 41.2 $7.3
21. UN!i CAPACITY FACTOR (USlkG MDC Nti) 90.8 34.4 60.3
22. UNii CAPACITY FACTOR (USING DtR hti) P9.9 34.0 49.8

............ ............ ............ {

23. UNii FORCID OUTAGE RATC 0.6 23.3 14.6  ;

............ ............ ............ i

- 24. %HUTD0VNS SCHCOUltD DVtR NEXT 6 MON 1Hs (ifP(, DAlt. AND DURAfl0N Or ( ACH); l' MIDCTCLE 3AIN1[ NANCE OUTAG(, START 1/25/92. 21 DAf$ DURA 110N .

l tt. IF $HUTD0VN AT INO OF REPORT t[R100. (511MAft0 DAT( OF $1AR10Pt N/A

26. UNji$ IN flli $1ATUS (PRIOR 10 COMMtRCI AL OPIRAtlCN): FORCCA$f ACH1[Vt0 IN!11AL CRITICALITY 09/15/73 INITIAL LL(CTRICITY 02/18/74 COMMtRCIAL OFLRATION 07/05/14 P/0C 2 Or ?

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- 4 OP[RAllNG DATA ttPORT i

DDCLt1 h0. 50 178 DAf t AUGU5t 15,1991 COMPl[T[D BY PHILADLLPHIA [ttC1RIC COMPANT M. J. BAADN SUPERVISOR R[POR15 GROUP PE ACH B0110M ATOMIC POWER STA110N TILIPHONE (117) 456+1014 (XI 3371 OrtRAllNG STA105

1. UN!1 hAMC2 PLACH B0T104 UN!1 3 NOT[5:
2. RfP0411NG FIR 100: JULY. 1991
3. L!CIN$t0 THIRMAL POWER (M/T): 3293
4. NAMEPL Aft RATING (GR055 kWI): 1152
5. DESIGN (LICTRitAtRATING(Nt1PWC): 1065 C. MAXIMUM D(PINDABLt CAPACITY (GR055 Mvt): 1098 I
7. MAXIMUM DtPthDABLE CAPAttif (h[i HWC): 1035
8. IF CHANG [5 OCCUR IN CAPACITY RATINGS (IlIMS f;UMDER 3 THROUGH 7) 5!NC[ LA51 RtPORT. GIVC RIAS-
9. POVtR LtVIL 10 VH]CH R[5TRICT[D. IF ANY (N(T MV()
10. REASONS FOR RISTRIC110N5. IF ANY i

THIS MONTH Yk.TO DATE CUNULA11VE 11, HOURS IN RIPORilNG P[RIOD i 744 5.087

~

............ 145.559

12. NUHe[R OF HOURS REACTOR WAS Crit! CAL 606.4 4.790.7

- 89.293.6

13. RfAC10R RE5[RVE SHUTDOWN HOURS 0.0 0.0 0.0 14.' HOUR 5 GCNfRATOR ON LINC - 587.7 4.157.5 86.248.1
15. UNIT RESIRVE 'JT00VN HOUR $ 0,0 0.0 0,0
16. GROSS ib(RMAi (N(RGY G[NfRAffD (M/H) 1.786.704 17.957.576 252.810.082 17.GR055 ELECTRICAL (NIRGYGEhERA1ED(FWH) 577.100 4.273.200 82.948,732
18. NET ILCCTRICAL [NERGY G[N(RAl[D (KWH) 550,662 4.114.891

............ 79.491.563 PAGE 1 0F 2 l

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t OttRAllNGDA1AAtPDR1(CONilNUID) DOCLif NO. $3 - 278 i

............................. t Daft AUGU$i 15. 1991 I

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THis NONTH YR 10 Daft COMJL AtlV(

19, UNIT SCRYlCL FACTOR 19.0 61.7 59.3

20. UN11 AVAICABitt1Y FAL104 79.0 81.7 59.3 f

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21. UNIT CAPAC11Y FAC104 (U$1NG HDC hti) h8 2 $h8

?!. UNji CAPAtliY FACTOR (USING DER kll)

............ ............ ............ f 69.5 76.3 51.3

.......... . ............ ............ i

23. UNIT FORCt0 OUTAGE RAlt 21,0 18.3 12.8
24. $HU100VMS 1CHIDDLID OvtR htXi 6 MONTH $ (ifPt. Daft. AND DURATION OF (ACH):

Rff Utt OUTAGE. START 9/14/91. 84 DAY 1 DURAtl0N

75. IF $HUTDOVN AT INu 0F REPORT FIR 100. Estl>AffD DAlt OF $7ARfDP1 N/A b

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26. UN115 IN TC$i STATUS (PRIOR 10 COMr.RCI AL OPERAi!ON): FORICA57 ACHitVfD 1 IN!!!AL CRITICAlltf  !

08/07/74  ;

INiilAL ILECTRICITY 09/01/74

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COMMERCIAL OPERATION lt/23/74 I, t

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UNIT $HUTODVNS AND POWER REDUCTIONS DOCAEi NO. 50 277 i

............................. t UNIT NAME PEACH B0ff0M UNii 2 r DATE AUGUST 15, 1991 REPORT MONTH JULY. 1991 COMPLETED BY PHILACELPHIA ELECTRIC COMPANY j

............................. t M. J. BARON {

$UPERVISOR i REPORIS GROUP I PEACH BOTTOM ATOMIC POVER STAi!0N  !

TELEPHONE (717)4$6-7014EXI.3321 i HETHOD OF E!CEN$EE SYSTEM COMPONENT CAU$[ AND CORRECilVE  ;

TYPE OURA110N REALON SHUTilNG DOWN EVENT CODE CODE AC(10N T0 NO. DATE (1) (HOURS) (2) REACTOR (3) REPORT # (4) t

..........................................................................(5)................. PREVENT RECURRENCE 7 910101 F 4.7 P 2 2 91-22 $[ VALV0P r

RECOMBINER 150LAi!0N - LOV i STEAM FLOV.  !

t 9 910703 F 0.0 A 4 N/A CB PUMPXX *A" RECIRC PUMP TRIP OVE TO BURNi LEAD 10 t MG SET EXClfER.

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-E (1) (2) (3)

I (4)

F - FORCEO

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REASON METHOD

$ - SCHEDULED EXHlBli G - INSTRUC110NS A - ;QUIPMENT FAILUP! (EXPLAIN) 1 . MANUAL FOR PREPAAATION OF CATA B - MAINTENANCE OR TEST 2 - MANUAL $ CRAM.

C - REFUEt1NG 3 - AUTOMATIC $ CRAM, ENTRY SHEETS FOR LICENSEE i D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

EVENT REPORT (LER) -f FILE (NUREG-0161) f E - OPERATOR TRAINING + tlCENSE EXAMINAT10N F . ADMINISTRATIVE (5) (

G - OPERA 110NAL ERROR (EXPLAIN) i H - 01HER(EXPLAIN) EXHIBil ! - SAME $0URCE  ?

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  • e UNif $ HUT 00VNS AND POVER REDUC 110N1 DOCKET NO. 50 + 278 UNIT NAME PEACH BOT 10M UNIT 3 DATE AUGUST 15, 1991 REPORT MONTH Julf.1991 COMPLETED BY PHIL ADELPHIA ELECTRIC C3HPANY M. J. BARON

$UFERVISOR REPORTS GROUP PEACH B0ff0M AfDMIC POVER STAil0N TELEPHONE (717) 456 7014 EXT, 3321

.................................... METHOD ........................................................................................

OF LICENSEC SY$1EM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON $ HUTTING ODWN EVENT CODE CODE ACTION 10

__ NO. DAtt (1) (HOURS) (2) REPORT f (4)

REACTOR (3) (5) PREVENT RECURRENCE 11 910707 F 156.3 A 3 3-91 10 RA CKiBRK GENERATDR LOAD UNBALANCE DUE 10 LIGHTN!NG $TRIKE.

- 12 910721 5 0.0 H 4 N/A RB CONR00 CONTROL ROD ADJUSTMENT.

REACTOR NOT $ HUT DOVN, 13 9!0706 5 0.0 F 4 N/A HH HTEXCH VALVED 0U1 STH STAGE HEATER PfR GP 5.

REACTOR NOT SHUT DOVN, 156.3 (1) (2) (3) (4)

F - FORCED REASON METH00 5 - SCHEDULED EXHIBIT G - INSTRUC110N$

A - EQUIPMENT FAILLRE (EXPLAIN) 1 - MANUAL FOR PREPARAil0N OF DATA B MAINTENANCE OR TEST 2 . MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE-C . REFUELING 3 - AUTOMATIC SCRAM. CVENT 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) EXHIBli ! . SAME SOURCE 1

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