ML20043G563

Monthly Operating Repts for May 1990 for Peach Bottom Units 1 & 2.W/900614 Ltr

ML20043G563
Person / Time
Site:	Peach Bottom
Issue date:	05/31/1990
From:	Baron M, Miller D PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006200432
Download: ML20043G563 (14)

Text

CCN-90-14119

%,t PIIILADELPHIA ELECTRIC COMPANY Pr.ACll BCT!*IONI KIONilC POWF.R STATION  ;

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L R. D.1. Ilox 208 i Delta. Pennsylonia 17314 l

psacas morrou ns rosu or ascsttamca (717) 4$G7014 I t- D. B. Miller, Jr.

Vice PresMent Junc 14, 1990 Docket Nos. 50 277 50 278 l

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

SUBJECT:

Peach Bottom Atomic Power Station Monthly Operating Report i Gentlemen:

Enclosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of May 1990 forwarded pursuant to Technical Specification 6.91.d under the guidance of Regulatory Guide 10.1, Revision 4.

Sincerely, MM (%)(LhbbiY f DBM/AAF/M@JB: cmc Enclosure cc: R.A. Burricelli, Public Service Electric & Gas T.M. Gerusky, Commonwealth of Pennsylvania JJ. Lyash, USNRC Senior Resident Inspector T.E. Magette, State of Maryland T.T. Mart.in, Administrator, Region I, USNRC H.C. Schwemm, Atlantic Electric J. Urban, Delmarva Power INPO Records Center CQ590.NRC 900620o432 900531 7 ( l FDR ADOCK 0500r ,

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NItC Monthly Opeestions Sonnemary Peach Bottoni Atoanic Power Station May 1990

. UNIT 2 The unit legan the month at 50% power, increasing, recovering fre n an outage for replacing the generatet exciter tearings. On May 7, with power at 87%, the unit was indicating higher than normal electrical energy for its thermal output. The variance was caused t>y high icedwater flow indie.3 tion which affected power calculations.

Pow : was held to 99% until the feedwater flowinstrumentation was recalibrated. On May 14, the unit achieved 100% power and maintained thio level until May 30, when the unit took a scheduled load drop to 700 MWe for main steam isolation valve closure testing. The unit returned to 100% power after completion of the testing and ended the month at that power level.

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UNIT 3 The unit legan the month at 80% power because of condenser performance probicans, Deguding condentcr

. formance, related to rising river water temperatures and having the 3C circulating water psmp out of service,

{imited power to a range of 84% to 94% for the entire month.

On May 16, the unit experienced a trip of the 'A' recirc MO set during rebrushing, and a consequent hd drop to approximately 500 MWe. Rebrushing was completed and the pump was restarted within the hour.

The unit ended the month at 94% power with work on the 3 *C" circulating pump continuing.

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i Docket No. 50 277 Attachment to Monthly Operating

.. Report for May 1990

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UNIT 2 REFUELING INFGKMATION 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 le?

Reload amendments for cycle 8.

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

Yo be determined. j

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier,  ;

unreviewed design or performance analysis methods, significent changes in fuel design, new operating -

procedures:

In order for PECo to do reload licensing anwyses in house for Unit 2 Cycle 9, NRC approval of one report (PECO FMS 006) must be obtained by May 31,1990. This report is the last in a series of six reports to demonstrate PECo's ability to perform the analyses. The report has been submitted and is expected to be approved in June 1990.

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7. The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:

I (a) Core 764 Fuel Assemblies (b) Fuel Pool 17M Fuel Assemblics,58 Fuct Rods CcE90.NRC I

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Attachment to Monthly Operating Report for May 1990 ,

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UNIT 2 REFUELING INFORMATION (Continued)

L, 8. The present licensed spent fuel pool storage capacity and the size of an increase in licensed storage l capacity that has been requested or is planned, in number of fuel assem ilics:

The spent fuel pool storage capacity has been relicensed for 3819 fuel auemblics, i i

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9. The projected date of the last refuelit.g that can be discharged to the spent fuel pool assuming the  !

. present capacity: 1 September 2003 without full core offload capability, t-  ;

September 1997 with full core offload capability. .j l

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r Docket No. 50-278 Attachment to Monthly Operating Report for May 1990 UNIT 3 REnfELING INFORMATION

1. Name of facility:

Peach Ilottom Unit 3

2. Scheduled date for next refe $. down:

Reload 8 schedul -j for Ai> 31,1991

3. Scheduled date for restart fo. ' Ang refueling Restart following refueling scheduled for Novemter 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?

Reload unendments 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 supplict, !

unreviewed design or performance analysis methods, signifit. int changes in fuct design, new operating

• procedures: i in order for PECo to do reload licensing analyks in house for Unit 3 Cycle 9, NRC approval ' [

of one report (PECO FMS 006) must be obtained by May 31, D90. Th:s report is the last in a series of six reports to demonstrate PECo's ability to lerform the analyses. The report has been submitted and is expected to be approvnt in June 1990. ,

7. The numter of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:  ;

(a) Core - 764 Fuel Assemblics (b) Fuct Pool- 14% Fuel Assemblics,6 Fuel Rods CC0590.NRC

Docket No. S278 Attachment to Monthly Operating Report for May 1990 Page 2 UNIT 3 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 been requested or is planned, in number of fuel assemblies:

The spent fuel pool storage capacity has been reticensed for 3819 fuel assemblics. Modification of the fuel pool is expected to be 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 '

prer.cnt capacity:

With the current fuel pool capacity (prior to the completion of the fuel pool teracking modification):

September 19'Xi 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 complet(ion of the fuel pool rcrackini September 2004 without full core offload capability.

September 1998 with full core ofiload capability.

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", i li AVERA6C DAILY UNIT POWIR'LEVtt  !

s DOCKET NO. 50 - !?? t i

, UNIT PLACH BOTTOM UNIT 2' l i

DATE JUNE 15. 1990 '

l COMPANY PHILADELPHIA LLECTRIC COMPANY {

r M. J. BARON  ;

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. SUPERVISOR

- RLPORTS GROUP PEACH BOTTOM ATOMIC POWER $1AT10N j-l

'j illtPHONE(717)45b7014EKT,3321 .

MONTH MAY 1990 ,

t DAY AVERAGE DAILY POWER LEVEL DAY- AVERAGE DAILY POWER LtVEL (MWi-Nti) (MWE4ti)

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1 610 17 1061 ,

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. 2: 7 04' 18 -1063 :l A

3' 813 19 1063 m. -

4- 842 20- 1065  :

% -, .5 874 - 21 1062 .!

6 945'  !! 1065 t 1

I 7 951 23 1061 8 1030 t4 1060 Jl t

.9 1028 ft 1061

.i 10 1044 '26 1062' O  :

11 1047  !? 1062  :-: 1 12 1048 28 1066 :f

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"' '993 14 1054. 30 .:[

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15- 1061 31 1038 l

.i 16 1065 1

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AVERAGE DA!LT UNIT POWER LEVEL 00CKti NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE JUNE 15, 1990 COMPANY PHILADELPHIA [L(CTRIC COMPANY M. J. BARON

$UPIRVISOR

-l- REPORTS GROUP PEACH P3TTOM ATOMit POWER STATION TELEPHONE (117) 455-7014 EXT. 3321

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MONTH MAY 1990 DAY AVERAGE DAILY POWER L(VEL DAY AVERAGE DAILY PDCtR LEVEL ~

. (MWi-N[T) (MWi-NET) 1 902  !? 873 2 825 18 875 -

' ' 870 3 823 19 4 869 20 873 5 875 21- 877-6 877 22 922

) 4 7 863 23 9 54 8 872 24 981

, 9- 871 25 969 e

L . 10 875 26 962 875 27 966 12 875 28 '966 h~ 13 881 29 954 14 ' 882 30 938 l 15 869 31 955 V ,

16 803

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OPERATING DATA R[PDRi DDCKET No. 50 - 277 Daft JUNE 15, 1990 CDNPLET[0 8Y PHILADELPHIA (LICTRIC COMPANY M. .l. 8 ARON

$UPERVISDR REPDRTS GROUP PEACH BOTTOM AfDMIC PDWER STATION TELEPHONE (717) 456-7014 EXT. 3321 OP(RATING STATU$

1. UN!i NAME: PEACH 80TfDM UNIT 2 N0ft$

2. R(PDRTING PERIOD: MAY, 1990

3. LICEN$tD THERMAL PDWER(MWT): 3293 4.NAMCPLATERATING(GROS $MWE): 1152

6. DESIGN CLECTRICAL RATING (kET MWE): 1065

6. MAXIMUM DEPENDA8LE CAPACITY (GROS $ MWE): 1098

7. MAXIMUM 0(PENDA8LE CAPACITY (NET MWE): 10$$

8.' IF CHANGES OCCUR IN CAPACITY RATINGS (litMS NUMBER 3 THROUGH 7) $1NCE LAST REPORT, GIV! REASDN$3.

9. PDWER LEVEL TO WHICH RISTRICTED, IF ANY (NET MWE):

10. REA$DNS FDR RESTRICTIONS, IF ANY:

THis MONTH YR-TD-DATE CUMULAllVE

11. HOUR $ IN REPDRi!NG PIRIOD 744 3,623 139,439

12. NUMBER Or HOUR $ REACTDR WAS CRITICAL 744,0 2,299.4 81.826.7

~ 1!, REACTOR RESERVE SHUTDOWN HOUR $ 4 0.0 0.0 0.0

14. HDUR$ GENERATDR ON-LINE 744.0 2,189.5 78.794.8

15. UNIT RE$ERVE SHUTDOWN HDUR$-= 0.0 0.0 0.0 16, GROS $ THERMAL ENERGY GENERATED (MWH) 2,309,184 6,359,808 231,650,001

17. GROS $(LECTRICALEWERGYGENERATED(MWH) 771.800 2,092.000 76,151.890

.'18. NET ELECTRICAL ENtRGY GENERAllD (MWH) 744,164 2,015.288 72,870.137 I

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OPERATING DATA REPORT (CONTINUED) 00CKli NOJ 50 - 277' Daft JUNE 15, 1990 i t

THl$ MONTH YR-TO-Daft CUMJLATIVE ,

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19. UNIT $tRVICE FACTOR 100.0 60.4 $6.5  :

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20. UNif AVAllABillfY FACTOR 100.0 60.4 $6.5  !

21. UNIT CAPAClfY FACICR (U$1NG MDC Nti) 94.8 $2.7 . 49.5 j

22. UNif CAPAC!1Y FACTOR (U$1NG DER Nti) 93.9 $2.2 -49.1 f

23. UNIT FORCCD OUTAGE RATE 0.0 25.1 14.8 ..,

24. $ HUT 00WN$ $CHEDULLO OVER NEXT 6 MONTH $ (fYPI,' DAf t, AND DURA 110N OF [ACH):

25, IF $HUIDOWN AT (ND OF REPORT PERIOD, ($11 MATED Daft OF STARTUP:

26. UNif$ IN T[$i $TATU$ (PRIOR 10 COMMERCIAL OPERAtl0N): FORtCA$f ACH!tVED  ?

IN!114L CRITICAllfY 09/16/73

• INITIAL [t[CTRICITY 02/18/74  ;

- COMMERCIAL OPERATION 07/0$/74

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OP[ RATING DATA REPORT i'

00CKET NO. 50 - 278 DATE JUNE 15, 1990 COMPLtilD BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON P 2

$UPIRVISOR h REPORTS GROUP i PEACH BOTTOM ATOMIC POWER $1AT10N TILIPHONE (FIF) 456-7014 EXT. 3321 OPERATING $fATU$

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1. UNIT NAME: P(ACH 80TfDM UNIT 3 N0Ttst i

2. REPORTING P(P100: MAY, 1990 I-. 3. LICEN$lD THERMAL POWER (WT): 3293-

4. NAM (PLATE RATlNG (GRD$$ WC): 1102 l

5. Ot$1GN [LECTRICAL RAi!NG (NET WC): 106L

6. MAXIMUM DfPENDABLE CAPACITY (GROS $ WE): 1098

7. MAX! MUM DCP(NDABLE CAPAClfY (NET MWE): 1035 t

8. IF CHANGES OCCUR IN CAPACITY RATINGS (IT[M$ NUMBER 3 THROUGH 7) $1NCE LAST REPORT, GIV[ RIA$0NS ' 2

9. POWER LEVEL 10 WHlCH Ri$TRICTED, if ANY (hti WE): j APPROXINAl[LY 980 WE

10. R(A$0N$ FOR Rt$iRICil0NS, IF ANY: l DEGRADED COND(N$lR PERFORMANCE RELAlt0 TO ONE OUT OF-$(RVICL CIRCULATING WATER PUMP AND RI$1NG )

I RIVER WAT[R 1[MPIRATURC.

l THl$ MONTH YR-10-0 ATE CUMULATIVE

11. HOUR $ IN R[ PORTING P[RIOD 744 3,623 135,335  :

12. NUMBER OF HOUR $ REAC10R WAS CRITICAL 744.0 3,454.5 80,613.3 l 7

0.0 0.0 0.0

13. REACTOR R[$tRVE SHUTDOWN HOUR $

14. HOUR $ G(N[RATOR ON-LINE 744.0 3,386.8 77,789.0 i

15. UNil R[$ERVE $HUTDOWN HOUR $ 0.0 0.0 0.0 16' GROS $ THERMAL [NERGYG[NERATED(MWH) 2,109,240 10.506,581 226,669,450 ,

17,GROSSELtCTRICAL[NERGYGENERAi[0(MWH) 090,500 3,480,800 74,352,932-18.NETELECTRICAL(NERGYGENERAT[D(MWH)- 666,56 3,372.900 71,215,468 t

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OPERATINGDATAREPORT(CONTINUED) DOCKET NO.'$0 - 278 DATE JUNE 15, 1990 THIS MONTH YR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 93.5 $7.5

20. UN!1 AVAILABILITY FACTOR 100.0 93.5 $7.5 ,

21.L*1fCAPACITYFACTOR(U$1NGMDCNE!) 86.6 89.9 $0.8

22. UNIT CAPACITY FACTOR (U$!NG DER NET) 84.1 87.4 49.4

23. UNIT FORCED OUTAGE RATE 0.0 6.5 13.0

24. $HuiDOWN$ $CHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH):

MID-CYCLE MAINTENANCE CUTAGE STARTING OCTOBER 27, ,

SCHEDULED FOR 21 DAYS, e

25. IF $HUIDOWN AT END OF REPORT PERIOD EST! MATED DATE OF STARTUP:

26.' UNITS ]N TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED l

INITIAL' CRITICALITY 08/07/74 ,

INITIAL ELECTRICITY 09/01/74 COMMERCIAL OPERATION '12/23/74  ;

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UNIT SHUTDOWN $ AND POWER REDUCTIONS DOCKCT NO. $0 - 277 UNIT NsME PEACH BOTTOM UNIT 2 DATE JUNE 15, 1990

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REPORT MONTH MAY 1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY t- M. J. BARON

• $UPERVISOR  !

REPORTS GROUP .

PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (117) 4$6-7014 EXI. 3321 L ,

METHOD OF' LICENSEE $YSTEM COMPONENT CAUSE AND CORRECTIVE .t L TYPE DURATION REASON SHUTTING 00WN EVENT CODE CODE ACTION TO -+

i' . NO. DATE (1) (HOURS) (2) REACTOR (3) . REPORT f (4) .(5) PREVENT RECURRENCE 7 900$05 $ 0.0 H 4 N/A RB CONROD FINAL CONTROL R00 ADJUSTMENT FOR FULL POWER ROD PATTERN. REACTOR WAS NOT .t I .

$ HUT DOWN. -l

-8 900$30 $ 0.0 B 4 N/A SD VALVEX MSiv TE$11NG. l P

-l (1)- -(2) -(3) (4)

F - FORCED - REASON . METHOD EXHlBIT G - INSTRUCTIONS

- $ - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL .

FOR PREPARAT!DN OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE .'

.-. -C - REFUELING 3 - AUTOMATIC $ CRAM. EVENTREPORT(LER) 0 D - 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 $0VRCE i

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UNIT $HUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 278 l UNIT NAME PEACH BOTTOM UNIT 3 i

DATE JUNE l$. 1990 l REPORT MONTH MAY. 1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY

!Y M. J. BARON i

-$UPERVISOR REPORTS GROUP l 1

PEACH BOTTOM ATOMIC POWER STAT!DN g TELEPHONE (?!?) 456-7014 EXT. 3321 l in i METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE buRATION REASON $ HUTTING DOWN EVENT CODE CODE ACTICt TO NO. DATE (1) (HOURS) (2) REACTOR (3) REPORT # (4) ($) PREVENT RECURRENCE j i

.$ 900$01 A 0.0' H 4 N/A HH ZZZZZZ POWER REDUCTION DUE 10 DEGGADED CONDENSER PERF'AMANCE. C CIRC VATER PUMP OUT OF

$ER',1CE. REACTOR WA$ NOT SHUT DOWN.

-6 900516 F .0.0 A' 4 N/A CB PUMPXX "4" RECIRC PUMP TRIP DURING BRU$H REPLACEMENT. REACTOR WA$ NOT '

$ HUT 00WN.

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g (1)- (2) (3) (4)

F - FORCEO REASON METHOD EXHIBIT G - INSTRUCTIONS

$ - $CHEDULED .A-EQUIPMENTFAILURE(EXPLAIN) 1 - MANUAL . FOR PREPARATION OF DATA p' B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY $HEET$ FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER)

O - REGULATORY RESTRICTION .

. 4-OTHER(EXPLAIN) FIEE(NUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE ($)

G - OPERATIONAL ERROR (EXPLAIN)

H-OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE :

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