ML20005G804

Monthly Operating Repts for Dec 1989 for Peach Bottom Atomic Station Units 2 & 3.W/900117 Ltr

ML20005G804
Person / Time
Site:	Peach Bottom
Issue date:	12/31/1989
From:	Baron M, Danni Smith PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9001230112
Download: ML20005G804 (14)

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- PHILADELPHIA ELECTRIC COMPANY I PEACil BCr!'IDM ATOMIC POWER STATION R. D.1, Box 208 t_

Delta, Pennsylvania 17314 h , reacu sortues-rue rowsm or xxcntswc - G17) 4567014

. D. M. 3mith '

C .Vice IWsident January 17, 1990 q

C- Docket Nos. 50 277 50 278 fi U.S. Nuclear Regulatory Commission -

- Document Control Desk -

-Washington, DC 20555 SUBJECI': 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 December 1989 forwarded pursuant to Technical Specification 6.9.1.d under the guidance ~of Regulatory Guide 10.1, Revision 4.

Sincerely, 7

fgg DMS/TEC/MJB: cmc Enclosure cc: R.A. Burricelli, Public Service Electric & Gas >

T.M. Gerusky, Commonwealth of Pennsylvania

. J.J. Lyash, USNRC Senior Resident Inspector T.E. Magette, State of Maryland W.T. Russell., Administrator, Region I, USNRC H.C. Schwemm, Atlantic Electri" J. Urban, Delmarva Power  ;

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CC1289.NRC 9001230.112 891231 [ "

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NRC Monthly Operations Summary Peach Bottom Atomic Power Station December 1989  ;

UNIT 2 Unit 2 began the month with the mode switch in refuel and pre-startup activities in progress, The unit had been shut down in late November because of a packing leak on the RCIC discharge valve. The unit was returned to 100% power on December 3. Power reductions were taken to complete repairs to the RCIC discharge valve, the "C" RFP discharge check valve and condenser waterboxes. The unit returned to 100% power on December 17.

A reactor scram occurred on December 20 during routine APRM testing. The unit recovered from the scram and reached 89% power on December 25. Power reductions occurred in order to repair a leak in the 'C" RFP-instrument line; repair of an indication in the 'A' RFP motor gear unit; control rod pattern adjustment and condenser waterbox maintenance. The unit returned to 100% power on December 30.

UNIT 3 Unit 3 began the month at 450 psig with power ascension activities in progress. Rated pressure was achieved

, on December 7 and the HPCI and RCIC systems were satisfactorily tested. Initial generator synchronization l ,; occurred on December 11 and the unit reached 33% power on December 13.

Power was increased to 72% on December 19. Power was subsequently reduced as an automatic runback i- occurred after the "C" RFP tripped because of high vibration. The runback was reset and the unit returned to 70% power. Power levels for the remainder of the month varied as problem investigation and repairs to the reactor feed pumps occurred. The unit ended the month at approximately 70% power.

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e ie Docket No. 50-277.  !

Attachment to .

Monthly Operating-  ;

Report for December 1989  ;

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, UNIT 2 REFUELING INFORMATION --  !

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1. Name of facility: [

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Peach Bottom Unit 2 '

2. Scheduled date for next refueling shutdown: <

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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?

No, .

If answer is yes, what, in general, will these be?

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

.Not applicable,

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:

l In order for PECo to do reload licensing analyses 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

scheduled for completion in May 1990. l 1

1

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

(a) Core - 764 Fuel Assemblics L- (b) Fuel Pool - 1734 Fuel Assemblies,58 Fuel Rods CC1289.NRC i.

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Docket No. 50-277 Attachment to -

Monthly Operating Report for December 1989 Page 2 UNIT 2 REFUELING INFORM ATION (Continued)

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

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 present capacity:

September 2003 without full core offload capability.

September 1997 with full core offload capability.

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Docket No,50-278 i Attachment to  !

, - Monthly Operating F

Report for December 1989 E

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i . UNIT 3 REFUELING INFORMATION  !

1. Name of facility:

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. Peach Bottom Unit 3 ' '

, 2.1 Scheduled date for next refueling shutdown: .<

' Reload 8 scheduled for August 31,1991 i

l 3. 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? ,

No.

If answer is yes, what, in general, will these be?

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

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:

None expected.

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Docket No. 50-278 Attachment to ,

7 Monthly Operating -  ;

Report for December 1989 i

,. ' Page 2 UNIT 3 REFUELING INFORMATION (Continued) }

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 14% Fuel Assemblies,6 Fuel Rods -

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, m number of fuel assemblies:  :

The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies. 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 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.

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AVERAGE DAILY UNIT POWER LEVELi- '

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. UNIT PEACH BOTTOM UNIT 2- -i k ,

' DATE JANUARY 15 11989-- T i

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~.4" / ' 5UPERVISOR- 1 REPORTS GROUP 3

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F -DAY AVERAGE DAILY POWER LEVEL . DAY - AVERAGE DAILY POWER LEVEL p (MWE-NET). (MWE-NET) l'- '0~ -17 1071 i

i I~2 0 18- 1074 l

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3'- 0- .19 - 1074 .

r 4. 524 20 801 5 863' 21 0

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. 7 1022- 23 24 8 .929 24 691

-9 -987 25- 910

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~ 10 1039 26 905  ;

11 .1051 27 848

--i 12 1071 28 858 13 1065 29 823 14 1067 30 999 15 -769 31 1072 '

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' AVERAGE DAILY UNIT POWER LEVEL'.

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COMPANY PHILADELPHIA ELECTRIC COMPANY A

W M. J. BARON E

SUPERVISOR 1 =

REPORTS GROUP

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DAY AVERAGE DAILY' POWER LEVEL' OAY= AVERAGE DAILY POWER LEVEL:

(MWE-NET) (MWE-NET) 1 0 17. 462 2

0' 18 63 0 3~ ..: 0 19 710-4 0 20 692 5 .0 21 -667 6 0 22 672 7 -' 0 23 - 725.  !

8 0 24 723 9 0 25- 590 10 - 0. 26 466 t 11 8 27- 470 a

12 -120- 28 585 +

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13 '152 29 502 e 14 278 30 712

'15 257 31- 594 16' 388 l

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0PERATING DATA REPORT o

y o DOCKET NO. 50 - 277 DATE JANUARY 15, 1989 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY

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M. J. BARON

s. SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STAil0N TELEPHONE (117) 456-7014 EXT. 3321 OPERATING STATUS

l. UNIT NAME: PEACH BOTTOM UNIT 2 NOTES:

2. REPORTING PERIOD: DECEMBER. 1989 (i- 3.LICENSEDTHERMALPOVER(MWT): 3293

-4.NAMEPLATERATING(GROSSMWE): 1152 5.DESIGNELECTRICALRATING(NETMWE): 1065 i i

6.HAXIMUMDEPENDABLECAPACITY(GROSSMWE): 1098 1055

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7.MAXIMUMDEPENDABLECAPACITY(NETMVE):

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g 8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

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9. POWER LEVEL TO VHICH RESTRICTED, IF ANY (NET MWE):  !

10. REASONS FOR RESTRICTIONS,' IF ANY:

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TH13 MONTH YR-TO-DATE CUMULATIVE i

11. HOURS IN REPORTING PERIOD 744 8,760 135,816

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12. NUMBER OF HOURS REACTOR WAS CRITICAL 639.2 5,330.5 79,527.3

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 <

14. HOURS GENERATOR ON-LINE 599.4 4,738.5 76,605.3 .

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 '

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16. GROSS THERMAL ENERGY GENERATED (HWH) 1,742,664 12,485,448 225,296,193

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17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 580,300 4,040,660 74,059.890 '

18. NET ELECTRICAL ENERGY GENERATED (MVH) 561,216 3,862,733 70,854,849 PAGE 1 0F 2 i'

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m h OPERATINGDATAREPORT(CONTINUED)' DOCKET NO.L50~- 271--

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-DATE JANUARY.15, 1989

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THIS MONTH ~ YR-TO-DATE CUMULATIVE.

h P 19.~ UNIT SERVICE FACTOR ^ 80.6- 54.1' 56.4 -

t:3 -20. UNIT AVAILABILITY FACTOR 60,6 54.1. 56.4

21. UNIT CAPACITY FACTOR (USING MDC NET) 71.5 '41.8 49.4

22. UNIT CAPACITY FACTOR (USING DER NET) 70.8 41.4 -49.0

23. UNIT FORCED OUTAGE RATE 19.4- 11.7 14.5

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):'

- MID-CYCLE MAINTENANCE OUTAGE BEGINNING 3/1/90. LASTING 3 WEEKS.

25i 1F SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

26.UNITSINTESTSTATUS(PRIORTOCOMMERCIALOPERATION): FORECAST- ACHIEVED ,

INITIAL' CRITICALITY. 09/16/73  :.

i-INITIAL ELECTRICITY 02/18/74

' COMMERCIAL' OPERATION 07/05/74 c.:

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CPERATING DATA REPORT DOCKET NO. 50 - 278 h DATE JANUARY 15, 1989 p ,

COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON

,' SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EKT. 3321-OPERATING STATUS

1. UNIT NAME: PEACH BOT 10M UNIT 3 NOTES: MODE SVITCH PLACED IN

2. REPORTING PERIOD: DECEMBER, 1989 START-UP ON NOVEMBER 19.

p 3. LICENSED THERMAL POWER (MWT): 3293 POWER ASCENSION ACTIVITIES

4. NAMEPLATE RATING (GROSS MWE): 1152 IN PROGRESS.

5.DE!!GNELECTRICALRATING(NETMWE): 1065 6.MAXIMUMDEPENDABLECAPACITY(GROSSMWE): 1098 7.MAXIMUMDEPENDABLECAPACITY(NETMWE): 1035

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) $1NCE LAST REPORT, GIVE REASONS:

9. POWER LEVEL TO VHICH RESTRICTED, IF ANY (NET MWE):

10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744 8.760 131.712

12. NUMBER OF HOURS REACTOR VAS CRITICAL 636.0 801.4 77.158.8

13. REACTOR RESERVE SHUT 00VN h0VRS 0.0 0.0 0.0 g 14, HOURS GENERATOR ON-LINE 472.9 472.9 74,402.2 l i

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 '

883,968 883,968

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16. GROSS THERMAL ENERGY GENERATED (MWH) 216,162,869

17. GROSS ELECTRICAL ENERGY GENERATED (MVH) 260.700 P60,700 70,872,132

18. NET ELECTRICAL ENERGY GENERATED (MWH) 247,314 189,313 67,842,468 PAGE 1 0F 2 l

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OPERATING DATA REPORT (CONTINUED) DOCKET NO. 60 - 278 DATE JANUARY 16, 1989 THl$ MONT68 YR-10-DATE CUMULATIVE

19. UNIT $[RVICL FACTOR 63.6 6.4 $6.5

20. UNIT AVAILA21LITY FACTOR 63.6 6.4 $6.5 21.UNITCAPACITYFACTOR(U11NGMDCNET) 32.1 2.1 49.8 22.UN'.TCAPACITYFACTOR(U$INGDERNET) 31.2 2.0 48.4

23. UNIT FORCED OUTAGE Raft 1.6 1.5 13.3

24. $HUTDOWN$ ICHEDULED DVER NEXT 6 MONTHS (TYPt Daft. AND DURATION OF [ACH):

25. IF $HUTDOWN AT END OF REPORT PERIOD, EST! Haft 0 Daft 0F $1ARTUP:

26. UNIT $ IN TEST STATUS (PRIOR TO COMMERCIAL OPERATJON): FORLCA$T ACHl[VID INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/14 COMMERCIAL OPERATION 12/23/74 PAGE 2 0F 2

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i UNIT $HUTDOWNS AND POWER REDUCTION $ DOCK [T NO. $0 - 278 .

i UNIT NAME PEACH BOTTOM UNIT 3 DAT[ JANUARY 15. 1989 REPORT MONTH DECEMBER. 1989 COMPLET[D BY PHILADELPHIA [LECTRIC COMPANY b M. J. BARON I: $UPERVISOR REPORTS GROUP .,

PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717)456-7014 EXT.3321 :j i

NETH00 0F LICEN$tt $YSTEM COMPONENT CAU$t AND CORRECTIVE TYPt DURATION REASON $ HUT 71NG DOWN [ VENT CODE CODE ACTION TO NO. DATE. (1) (HOUR $) (2) REACTOR (3) REPORT f (4) ($) PREVENT RECURRENC[ l 7 891201 $ 2$4.0 C 1 N/A RC FUELXX CONTINUATION OF RtFUEL DUTAGE B 891211 F 7.4 A 4 N/A HA TURBIN TURBINE TRIP DUE 70 HIGH VIBRATION. i REACTOR WAS NOT $Htif DOWN. t

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9 691212 $ B.B B 4 N/A HA TURBIN TURBINE IRIP PER RT $ 21.

REACTOR WAS NOT $ HUT DOWN.

10 891213 $ .9 8 4 N/A HA TURBIN TURBINE TRIP P[R RT 6.21.

REACTOR V7,$ NOT $HUi DOWN.

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11 891221 F 4.$ A 4 N/A CH PUMPXX C REACTOR FitD PUMP VIBRAi10N.

REACTOR WAh NOT SHUT DOWN. i 12 89122$ F 72.0 A 4 N/A CH PUMPXX

' B REACTOR FEED PUMP V!BRATION. ~

REACTOR WA$ NOT SHUT DOWN.  !

-13 891229 F 17.5 A 4 N/A CH VALVtX PRES $URt RELl[F VALVE FAILURE ON "A" [

FEED PUMP. REACTOR WA$ NOT $ HUT DOWN. ,

14 891230 $ 2.0 B 4 N/A CB PUMPXX A REACTOR R[ CIRC PUMP TRIP FOR MAT 1536. '

RfACTOR WAS NOT $ HUT DOWN.  !

1$ 891231 $ 9.5 8 4 N/A CB PUMPXX B REACTOR RECIRC PUMP TRIP FOR MAT 1$36. )

REACTOR WA$ NOT $ HUT DOWN.  !

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, F - FORCED REASON METHOD [XHlBIT G - INSTRUCTIONS l $ - $CHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARAfl0N OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC $ CRAM. EVENTREPORT(LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN) FILE (NUREG-0161)

(: E - OPERATOR TRAINING + LICENS[ EXAMINATION F - ADMINISTRATIVE ($)

6-OPERATIONALERROR(EXPLAIN) l H - OTHER(EXPLAIN) EXHIBIT I - SAME $0VRCE

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l p UNIT $HUTDOWN$ AND POWER REDUCT!DN$ DOCKET NO. M - 277 .i UNIT NAME PEACH BOTTOM UNIT 2- ,

I DATE JANUARY 1$ 1989 REPORT MONTH DECEMBER, 1989 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVl$0R REPORTS GROUP i~ ' PEACH BOTTOM ATOMIC POWER STAtl0N  :

TELEPHONE (117) 4$6-7014 EXT. 3321 1

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, METHOD OF LICENSEE SYSTEM COMPONENT CAU$E AND CORRECTIVE  !

H TYPE DURATION REA$0N $ HUTTING DOWN EVENT CODE CODE ACfl0N TO NO. DATE (1) (HOUR $) (2) REACTOR (3) REPORT f (4) ($) PREVENT RECURRENCE -

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,a 16 891201 F 70.$ A 2 28930 CE VALVEX STEAM LEAK IN RCIC DISCHARGE CHECK VALVE.

!} (A0-2-13-22).  !

~ 17 891207 F $.0 A 4 N/A CH VALVEX STEAM LEAK IN C REACTOR FEED PUMP Ol$ CHARGE- t CHECK VALVE. REACTOR WAS NOT $ HUT DOWN.  ;

I '18 89121$ '$ $.3 8 4 N/A HC HTEXCH WATERBOX MAINTENANCE. .h REACTOR WAS NOT $ HUT DOWN.

19 89122) ~F 74.1 6 3 28933 IE INSTRU APR'1 FUNCTIONAL ERRnR,  ;

i 20 891227 F 1.8 A 4 N/A CH PIPEXX STEAM LEAK IN C REACTOR FEED PUMP DISCHARGE [

L. FLOW (LEMENT LINE. REACTOR VAS NOT $ HUT DOWN. 'I

,21 891228 $ 6.0 - B 4 N/A HC HTEXCH WATERBOX MAINTENANCE.

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REACTOR WAS NOT $ HUT DOWN. -

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F - FORCED RU$0N METHOD EXHIBIT G - INSTRUCil0NS

$ - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA ,

B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY $HEET$ FOR LICENSEE C - REFUELING 3 - AUTOMATIC $ CRAM. EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4-OTHER(EXPLAIN) FILE (NUREG-0161) ,

E - OPERATOR TRAINING + LICENSE EXAMINATION  ;

F - ADMINISTRATIVE ($)

6 - OPERAil0NAL [RROR (EXPLA]N)

H-OTHER(EXPLAIN) EXHIBli ! - SAME SOURCE 7 ,

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