ML19325D806

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Monthly Operating Repts for Sept 1989 for Peach Bottom Units 2 & 3.W/891013 Ltr
ML19325D806
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 09/30/1989
From: Baron M, Danni Smith
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8910260205
Download: ML19325D806 (14)
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? PHILADELPHIA ELECTRIC COMPANY PEACil IK7f10M ATOMIC POWER STATION i R. D.1, Iku 208 Delta. Itnnsylvania 17314 p.,a poo i a or a ununc a pl7) 456-7014

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sadth asiriu October 13, 1989 Docket Nos. 50-277 50 278 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 September 1989 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Sincerely kT6 DMS/TEC/(MJB:

Enclosure f/ cme cc: R.A. Burricelli, Public Service Electric & Gas T.M. Gerusky, Commonwealth of Pennsylvania T.P. Johnson, USNRC Senior Resident inspector T.E. Magette, State of Maryland W.T. Russell., Administrator, Region I, USNRC H.C. Schwemm, Atlantic Electric J. Urban, Delmarva Power INPO Records Center E

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1 CCN g'69 ,14166 : j e i. . ,

'g 4 PHILADELPHIA ELECTRIC COMPANY ,

d PEACil BOTIOM ATOMIC POWfR S1ATION .!

!~ R. D.1, Box 208 '

Delta, EYnnsylmila 17314 q

' PuCat Sm10e84tM POWBR Op 8 A0tLLtNcr (717)456 7014 l

. D. M. Smith 77

' Vice Proklent- .

October 13, 1989 7-e 1

Docket Nos. 50 277 50-278 j U.S. Nuclear Regulatory Commission Document Control Desk - '

Washington, DC 20555 I

SUBJECT:

Peach Bottom Atomic Power Station Monthly Operating Report q

I Gentlemen:

Enclosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of September 1989 forwarded pursuant to Technical Specification 6.9.1.d under the  ;

guidance of Regulatory Guide 10.1, Revision 4.

Sincerely i

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Enclosure h/ l j

cc: R.A. Burricelli, Public Service Electric & Gas l T.M. Gerusky, Commonwealth of Pennsylvania i T.P. Johnson, USNRC Senior Resident inspector T.E. Magette, State of Maryland i W.T. Russell., Administrator, Region I, USNRC 1 H.C. Schwemm, Atlantic Electric 1 J. Urban, Delmarva Power  !

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s' NRC Monthly Operations Summary Peach llottom Atomic Power Station September 1989 i

UNIT 2 Unit 2 began this reporting period at 100% power,3273 MWt, and 1073 MWe, L Unit power was reduced to 70% power on 9/3/89 to perform Main Turbine valve testing. Unit power was i returned to 100% after the testing was completed.

Unit power was reduced to 80% on 9/16/89 because of high feedwater copper content (greater than .4 ppb).

Feedwater copper content was reduced to a level acceptable for 100% power operation (less than .3 ppb) on 9/20/89. Urut power increase were stopped at 90% because the 'C' Reactor Feed pump controls were not as stable as expected. Further investigation indicated that the control problem was minor and 100% power operation was acceptable with the 'C' Reactor Feed pump. The Unit was returned to 100% and a plan was developed to correct the 'C' Reactor Feed pump in a few weeks.

HPCI was removed from senice on 9/26/89 to correct a problem with the 'Overspeed Trip Reset' mechanism.

The overspeed tripped properly but did not always auto reset after a trip occurred. HPCI was operable with this condition, however repairs were made to correct the problem and HPCI was returned to service on 9/28/89.

Unit 2 ended this reporting period at 99% power,3258 MWt, and 1082 MWe,

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UNIT 3 The unit remained shut down during the report period with modification activitics in progress.

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r. , 'h Docket No. 50 277 rl -

Attachment to (

Monthly Operating.

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Report for September 1989.,

UNIT 2 REFUELING INFORMATION ' j r

l .- 4  : 1. Name of facility:

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Peach Bottom Unit 2 l-

.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 6,1991

4. v

. Will refueling or resumption of operation therefore require a technical specification change or other i license amendment?

. .i No. ,

p ?- . If answer is yes, what, in general, will these be? '

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

Not applicable.

6.

a Important licensing considerations associated with refueling, e.g., new or different fuel design or suppli,er, unreviewed design or performance analysis methods, significant changes in fuel design, new operatmg '

procedures:

' In order for PECo to do reload licensing analyses in-house for Unit 2 Cycle 9, NRC approval of two reports (PECO FMS 005 and 006) must be obtained by May 31,1990. These reports are the last two .

L in a series of six reports to demonstrate PECo's ability to perform the analyses. Both reports haw been  !

[' submi:ted and are scheduled for completion In May 1990. '

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

1 n (a) Core - 764 Fuel Assemblics (b) Fuel Pool - 1734 Fuel Assemblies,58 Fuel Rods 1

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CC0989.NRC

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t L Docket No. 50 277 Attachment to i Monthly Operating r., _ Report for September 1989 .

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Uf IT 2 REFUELING INFORMATION (Continued)

8. The present licensed spent fuel pool storage capacity andh size of any tricrease 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. 50-778 L 4 L'

' . . Attachment to ,,

Mdthly Operating

- . . _ . . , ,_ Report for September 1989 * -

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y UNIT 3 REFUELING INFORMATION i

1. Name of facihty: _ . . _ _ _

Peach Bottom Unit 3

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T2.~ ~ Scheduled date'for next refueling shutdown: * - '^ '

L(1) ' Reload 7 in progress , -

(2). Reload 8 scheduled for August 31,1991

3. Scheduled date for restart following refueling

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(1) Restart following refueling forecast for October 27,1989 (2) Restart following refueling scheduled for October 29,1991 , , . . . , , , ,. . ,

t 4. W'!d refueling or resumption of operation thereafter require a technical specification change or other - '

license amendment? d Yes.

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

l (1) Cycle 8 Relosd Amendment l (2) Rod Sequence Control System / Rod Worth Minimizer Amendment l l

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

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(1) Cycle 8 Reload License Amendment submitted July 1988 (2) Rod Sequence Control Systen / Rod Worth Minimizer modification to reduce start-up time, submitted July 1989.

6. Important licensing consideratiots 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 Monthly Operating Report for September 1989 '

Page 2 UNIT 3 REFUELING INFORM ATION (Continued)

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 .14% Fuel Assemblics,6 Fuct Rods

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that he been requested or is planned, in number of fuel assemblies:

The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblics. This modification began on February 20,1987. The completion date for this modification has been  ;

rescheduled for the first quarter of 1990 to accommodate the Unit 3 outage.

9. . The projected date of the isst refueling that can be discharged to the spent fuel pool assuming the present capacity: '

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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 offload capability (est. January 1991).

With increased fuel pool capacity (subsequent to the completion of the fuel pool reracking modification):

Scotember 2004 without full core offload capability.

September 1998 with full core offload capability.

CC0989.NRC

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OPERATING DATA REPORT -

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DOCKET NO 50 - 277 -

DATE DCTOBER 15, 1989 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON .-

SUPERVISOR REPORTS GROUP i

PEACH BOTTOM ATOMIC POWER STATION i

TELEPHONE (717) 456-7014 EXT. 3321 OPERATING STATUS

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1. UNIT NAME: PEACH BOTTOM UNIT 2 NOTES: - - -
2. REPORTING PERIOD: SEPTEMBER, 1989

( 3. LICENSED THERMAL POWER (MWT): 3293

4. NAMEPLATE RATING (GROSS MWE):  !!52 I 5. DESIGN ELECTRICAL RATING (hET MWE): 1065
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): [055 -
8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) $1NCE LAST REPORT, GIVE REASONS: .
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
10. REASONS FOR RESTRICTIONS, IF ANY:

I THIS MONTH YR-TO-DATE CUMULATIVE  !

.i 11.' HOURS IN REPORTING PERIOD 720 6,551 133,607

12. NUMBER OF HOURS REACTOR WAS CRITICAL 720.0 3,440.6 77,637.4
13. REACTOR RESERVE SHUT 00WN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 720.0 2,921.9 74,788.7  ;
15. UNIT RESERVE SHUT 00VN HOURS 0.0 0.0 0.G

' 16. GROSS THERMAL ENERGY GENERATED (MWM) 2,268,936 6.863,112 219,673,857

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 752,700 2,181,060 72,200,290

............ ............ ............ l 18.NETELECTRICALENERGYGENERATED(HWH) 725,607 2,067,399 69.059.515 -)

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DATE OCTOBER 15, 1989 1"

THl$ MONTH YR 10 DATE -

CUMUL ATIVE ' -

l 19. UNIT $ERVICE FACTOR 100.0 44.'6 56.0' 4 p

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100.0 -44.6 56.0 - - --

21. UNIT CAPACITY FACTOR (USING MDC NET) 95.9 30.0 49.2

- 22, UNIT CAPACITY FACTOR (USING DER NET) 94.6 29.6 48.5 -e

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23. UNIT FORCED OUTAGE RATE 0.0 7.4 14.4- .

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

i; MAINTENANCE OUTAGE, 3/1/90, 20 DAYS.

25. IF $HUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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, , . ..26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERAT!DN): FORECAST ACHIEVED h' '

INITIAL CRITICALITY 09/16/73 L .

INITIAL ELECTRICITY 02/18/74

' COMMERCIAL OPERATION '07/05/N <-

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OPERATING DATA REPORT DOCKFT NO. 50 - 278 DATE SEPTEMBER 15, 1989 Cov/LETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON _ . .

SUPERVis0R REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION .

TELEPHONE (717) 456-7014 EXT. 3321 OPERATING STATUS

1. UNIT NAME: PEACH BOTTOM UNIT 3 NOTES: . UNIT 3 REMAINED SHUT DOWN . . .~ - .t
2. REPORTING PERIOD: SEPTEMBER, 198$ VITH MODIFICATION 3.LICENSEDTHERMALFDVER(MVT): 3293 ACTIVITIES IN PROGRESS.

4,NAMEPLATERATING(GROS $MVE): 1152 S.DESIGNELECTRICALRATING(NETMWE): 1065

6. HAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
7. HAX1 MUM DEPENDABLE CAPACITY (NET MWE): 1035

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

9. POVER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):

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10. REASONS FOR RESTRICTIONS, IF ANY: ,

t THis MONTH YR-TO-DATE CUMULATIVE s l 11. HOURS IN REPORTING PER100 720 6,551 129,503

12. NUMBER OF HOURS REACTOR VAS CRITICAL 0 0 76,357.4
13. REACTOR RESERVE SHUTOOWN HOURS 0.0 0.0 0.0 l 14. HOURS GENERATOR ON LINE 0.0 0.0 73,929.3

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15. UNIT RESERVE SHUT 00VN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 0 0 215,278.901 i

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17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0 0 70.611.432
  • -6,956
  • 67,605.984 18.NETELECTRICALENERGYGENERATED(MWH) -4f.171 I

PAGE 1 0F 2 l

  • NEGATIVE GENERATION PROVIDED FOR CONSISTENCY WITH FERC REPORTS.

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19. UNIT SERVICE FACTOR ' O.0 0.0' e.............57. I '.

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'20. UNIT AVAILABILITY FACTDR - 0.0 0.0 57,1 -

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(1 'o 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 . 0.0 :50.4 L-  : .

, , '22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 49.0

_. ............ ............ 6 ............ _ , . _ , , , , _ . _..,y 23.' UNIT FDRCED OUTAGE RATE 0.0 0.0 13.3

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. 25. IF SHUTDOWN AT END OF REPDRT PERIOD, ESTIMATED DATE OF STARTUP: ; NOVEMBER 15, 1989. ,

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INITIAL CRITICALITY 08/07/74 (

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' COMMERCIAL OPERATIDN 12/23/74- 4 , a->

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UNIT SHUT 00VNS AND POWER REDUCTIONS DOCKET NO. 50 - 277 UNIT NAME PEACH BOTTOM UNIT 2 r' DATE OCTOBER 15, 1989 REPORT MONTH SEPTEMBER, 1989 COMPLETED BY PHILADELPHIA ELECTRIC COMPANT 3, ............... .............................

M. J. BARON . . .

SUPERVISOR ,

REPORTS GROUP PEAC'l BOTTOM ATOHIC POWER STATION ,

TELEPHONE (117) 456-7014 EXT. 3321 METHOD OF. LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURAtl0N REASON SHUTTING 00VN EVENT CODE CODE ACTION TO NO. DATE (1) (HOURS) (2) REACTOR (3) REPORT f (4) (5) PREVENT RECURRENCE 10 890903 $ 021.0 B 4 N/A CD VALVEX MSIV TESTING REACTOR VAS NOT SHUT 00VN

'11 890916 F 095.5 H 4 N/A HH ZZZZZZ HIGH COPPER CONCENTRATION 4: REACTOR WAS NOT SHUT DOWN 116.5- .

(1) (2) (3) (4)

F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS '

S - SCHLOULED A-EQUIPMENTFAILURE(EXPLAIN) 1 . MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. [NTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTONATIC SCRAM. EVENTREPORT(LER)

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

E-- OPERATOR TRAINING + LICENSE EXAMINATION . o F - ADMINISTRAllVE (5)

G - OPERATIONAL [RROR (EXPLAIN)

H - OTHER(EXPLAIN) EXHIBIT I - 3AME SOURCE

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UNIT SHUTOOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 278

  • UNIT NAME PEACH BOTTOM UNIT * ,
DATE SEPTEMBER 15, 1989 r .............................  ;

i REPORT MONTH SEPTEMBER, 1989 COMPLE1ED BY PHILADELPHIA ELECTRIC COMPANY

............... ............................. 1 N. J. BARON - -

p SUPERVISOR ,

REPORTS GROUP ,

PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (117)456-7014 EXT.3321 i

METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE OURATION REASON SHUTTING 00WN EVENT CODE CODE ACTION TO NO. DATE (1) (HOURS) (2) REACTOR (3) REPORT # (4) (5) PREVENT RECURPENCE w

7 890901 S 720.3 C 1 N/A RC FUELXX CONTINUAT!DN DF REFUEL OUTAGE 720.0 .

(1) (2) (3) (4)

F - FORCEO REASON METHOD ' EXHIBIT 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 . REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER)

0. REGULATORY RESTRICTION .

4 - OTHER (EXPLAIN) FILE (NURE6-0161)

E . OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)

G-OPERATIONALERROR(EXPLAIN) ,

i H - OTHER(EXPLAIN)- EXHIBIT ! - SAME SOURCE

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