ML20045C018

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Monthly Operating Repts for May 1993 for Pbaps,Units 1 & 2. W/930615 Ltr
ML20045C018
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 05/31/1993
From: Baron M, Gelbich G, Miller D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CCN-93-14091, NUDOCS 9306210401
Download: ML20045C018 (14)
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CC10 93814091 PIIILADELPIIIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION p> ,%, R.D.1, Box 208

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1 Delta, Pennsylvania 17314 i nxu wnTou mit nun or rxcunscr (717) 456-7014 l D D Mdler. Jr.

Vice President June 15, 1993 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 Gentlemen:

Enclosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of May 1993 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Sincerely,

, jgf ) g / f 4 /N DBM/e \ /GHG/GDE/MSil: mss Enclosure cc: R.A. Burricelli, Public Service Electric & Gas W.P. Dornsife, Commonwealth of Pennsylvania JJ. Lyash, USNRC Senior Resident inspector a R.I. McLean,-State of Maryland T.T. Martin, Administrator, Region I, USNRC H.C. Schwemm, Atlantic Electric C.D. Schaefer, Delmarva Power INPO Records Center cownxnc

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.PDR R ADOCK 05000277PDR fh [ t}-

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. l NRC Monthly Operations Summary l Peach Bottom Atomic Power Station  :

May 1993 J l

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. UNIT 2 e

Unit 2 began the month at nominal 100% power. On May 19, operators reduced load to approximately 925 MWe due to loss of power supply to the E22 bus caused by the normal supply breaker tripping open. This caused a loss of extraction steam to "B" feedwater heater string and a GPII outboard isolation. After several hours of I

investigation into the cause of the tripped breaker the unit was returned to 100% power with the E22 bus being supplied from the #2 SUE. The E322 breaker trip was later found to be caused by a short circuit in an indicating light.  ;

UNIT 3 Unit 3 began the month at nominal 100% power. On May 7 power was reduced to approximately 440 MWe for condenser waterbox cleaning. Unit 3 was returning to 100% power on May 9th wh, . a problem with the #2 Tip Machine was discovered. Reactor power was held at 95% until further investigation of the problem could be conducted. After investigation it was determined by the Reactor Engineers that power could be increased to i 100%. On May 21st reactor power was again reduced to approximately 62% to facilitate repairs on the "A" i reactor feedwater pump and perform additional flux tilt testing. After repairs were completed the unit was returned to approximately 95% power on May 24th. This was due to the results of the flux tilt testing. As a conservative measure an asymmetric control rod was inserted to position 00 to suppress power in a leaking fuel

bundle. This rod pattern caused extra conservatisms in thermallimit calculations as well as a power reduction.

The unit was operated in a fuel coastdown mode for the remainder of May.

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e CC0593.NRC

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l Docket No. 50-277 1 Attachment to Monthly Operating  ;

Report for May 1993 UNIT 2 REFUELING INFORMATION

1. Name of facility: j Peach Bottom Unit 2
2. Scheduled date for next refueling shutdown:

Reload 10 scheduled for September 10,1994.

3. Scheduled date for restart following refueling:

Restart following refueling forecast for December 8,1994.

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:

N/A

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

N/A i

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i Docket No. 50-277 Attachment to Monthly Operating Report for May 1993 Page 2 UNIT 2 REFUELING INFORMATION (Continued) d

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

(a) Core - 764 Fuel Assemblics (b) Fuel Pool - 2164 Fuel Assemblies,58 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, 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 present capacity:

September 2003 without full core offload capability.

September 1997 with full core offload capability.

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CCO$93.NRC

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. l Docket No. 50-278 Attacl. ment to Monthly Operating Report for May 1993 UNIT 3 REFUELING INFOR51 ATION i

1. Name of facility:

Peach Bottom Unit 3

2. Scheduled date for next refueling shutdowm:

Reload 9 scheduled for September 11,1993

3. Scheduled date for restart following refueling Restart following refueling scheduled for November 14,1993
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?

92-19 Change safety limit MCPR for Cycle 10 ,

92-13 CAD analyzer replacement i

93-01 ARTS /MELLA 93-06 Drywell Rad Monitors

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

92-19 Sut5mitted February 1993

  • 92-13 Submitted February 1993 93-01 Submitted April 1993 ,

93-06 Scheduled for April 1993

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:

N/A ,

CG591NRC -7

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b Docket No. 50-278 Attachment to Monthly Operating Report for May 1993 Fage 2 UNIT 3 REFUELING INFORM ATION (Continued)

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

(a) Core - 764 Fuel Assemblies (b) Fuel Pool - 1945 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, 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 present capacity:

September 2004 without full core offload capability.

September 1998 with full core offload capability.

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CCC693.NRC

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AVERACE DAILY UNIT POWER LEVEL DOCKET No. 50 277 UNIT PEACH BOTTOM UNIT 2 DATE JUNE 15,1993 COMPANY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPEPVISOR REPORTS CROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 3321 MONTH HAY 1993 DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWE NET) (MWE-NET)

! 1 1052 17 1053 2 1052 18 1061 3 1055 19 1044 4 1062 20 1060 5 1051 21 1042

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6 1042 22 1041 7 1058 23 1056 8 1059 24 1064 9 1063 25 1064 10 1051 26 1060

, 11 1067 27 1055 12 1060 28 1064 13 1D49 29 1051 14 1061 30 1051 15 1057 31 1059 j 16 1056 e n c _ - _ . - - -_L----.-------_-L-.---. a> w . -

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AVERACE DAILY UNIT POWER LEVEL i

DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE JUNE 15, 1993 COMPANY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVISOR REPORTS GROUP PEACH EDTTOM ATOMIC POWER STATION l

TELEPHONE (717) 456 7014 EXT. 3321 MONTH MAY 1993 DAY AVERAGE DA1LY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET) (MWE NET)

$ 1 1052 17 1042 2 1051 18 1032 3 1045 19 1034 4 1062 20 1037 5 1036 21 1004 6 1027 22 660 7 903 23 806 8 443 24 972 5 9 875 25 975 10 996 26 966 11 1041 27 961 ,

12 1058 28 967 13 1019 29 950 ,

14 1041 30 958 15 1033 31 954 j 16 1037 ,

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4 OPERATING DATA REPORT DOCKET NO. 50 - 277 DATE JUNE 15,1993 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVISOR REPDRTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 3321 OPERATING STATUS

1. UNIT NAME: PEACH BOTTOM UNIT 2 NOTES:
2. REPORT!NG PER100: MAY, 1993
3. LICENSED THERMAL POWER (MWT): 3293
4. NAMEPLATE RATING (GROSS MWE): 1152
5. DESIGN ELECTRICAL RATING (NET HWE): 1065
6. KAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
7. MAX 1 HUM DEPENDABLE CAPACITY (NET MWE): 1055 3 8. IF CHANGES OCCUR IN CAPACITY RAT!NGS (ITEMS NUMBER 3 THROUGH 7) $1NCE LAST REPORT, GIVE REASON $:

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9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE): -i
10. REASONS FOR RESTRICTIONS, IF ANY:

THl$ MONTH YR-10 DATE CUMULATIVE 744 3,623 165,743

11. HOURS IN REPORTING PER100 ............

744.0 2,999.0 101,383.1

12. NUMBER Cf HOURS REACTOR WAS CRITICAL
13. REACTOR RESERVE SHUTDOWN HOURS 00 00 00
14. HOURS GENERATDR ON-LINE 744.0 2,842.0 97,491.2
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY CENERATED (HWH) 2,440,219 8,959,195 289,328,939 l

813,500 2,960,900 95,133,290.'

17. CROSS ELECTRICAL ENERGY GENERATED (MWH) ............-

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18. NET ELECTRICAL ENERGY GENERATED (MWH) 785,320 - 2,B67,347 91,154,066

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OPERATING DATA REPOR' (CONTINUED) DOCKET No. 50 - 277 DATE JUNE 15,1993 THl$ HONTH YR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 78.4 58.S
20. UNIT AVAILABILITY FACTOR 100.0 78.4 58.8
21. UNIT CAPACITY FACTOR (USING HDC NET) 100.1 75.0 52.1
22. UNIT CAPACITY FACTOR (USING DER WET) 99.1 74.3 51.6
23. UNIT FORCED DUTAGE RATE 0.0 7.0 14.3
24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
25. IF SHUTDOWN AT END OF REPORT PER100, EST! HATED DATE OF STARTUP: N/A
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 .

i INITIAL ELECTRICITY 02/18/74 COMMERCIAL OPERATION 07/05/74 ,

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4 OPERATING DATA REPORT b

DOCKET No. 50 - 278 r

DATE JUNE 15, 1993 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY

' M. J. BARON SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STAi.'.a TELEPHONE (717) 456 7014 EXT. 3321 OPERATING STATUS

1. UNIT NAME: PEACH BOTTOM UNIT 3 NOTE 5
2. REPORTING PERIOD: MAY, 1993
3. LICENSED THERMAL POWER (MWT): 3293
4. NAMEPLATE RATING (GROSS MWE): 1152
5. DESIGN ELECTRICAL RATING (NET MWE): 1065
6. MAXIMUM DEPENDABLE CAPACITY (GRCSS MWE): 1098
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1035
8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

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9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MVE):
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

11. HOUR $ IN REPORTikG PERIOD 744 3,623 161,639
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 3,523.0 101,581.4
13. REACTOR RESERVE SHUTDOWN HOURS ~ 0.0 0.0 0.0
14. HOURS GENERATOR ON LINE 744.0. 3,504.0 98,201.2
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 2,286,490 11,084,787 289,665,997
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 746,500 3,634,800 95,074,932
18. NET ELECTRICAL ENERGY GENERATED (MWH) 720,905 3,525,949" 91,189,915 PAGE 1 0F 2 b

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i OPERATING DATA REPORT (CONTINUED) DOCKET NO. 50 - 278 )

i DATE JUNE 15, 1993 i 5

THIS MONTH YR TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 96.7 60.8
20. UNIT AVAILABILITY TACTON 100.0 96.7 60.8 l
21. UNIT CAPACITT FACTOR (USING MDC NET) 93.6 94.0 54.5
22. UNIT CAPACITT FACTOR (USING DER NET) 91.0 91.4 53.0
23. UNIT TORCED DUTAGE RATE 0.0 3.3 12.4 .
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURAtl0N OF EACH):

- 2$. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 11/14/93

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26. UNITS IN TEST STATUS (FRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED ,

INITIAL CRITICALITT -08/07/74 INIT!AL ELECTRICITY 09/01/74 COMMERCIAL OPERAT1DN 12/23/74 b

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UNIT SHUTDOWNS AND DOWER REDUCTIONS DOCKET NO. 50 - 277 UNIT NAME PEACH BOTTOM UNIT 2 '

LATE JUNE 15,1993 REPORT MONTH MAY, 1993 COMPLETED BT PHILADELPHIA ELECTRIC COMPANY M. J. BARON TUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 3321 METHOD OF LICENSEE STSTEM COMPONENT CAUSE AND CORRECTIVE TTPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO No. DATE (1) (HOURS) , (2) REACTOR (3) REPORT # (4) (5) PREVENT RECURRENCE r '

14 930519 F 5.0 H 4 N/A EB CKTBRK LOS$ OF POWER TO E22 BUS DUE TO TRIPPING OF E322 BREAKER. REACTOR NOT SHUTDOWW.

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5.0 (1) (2) (3) (4)

F FORCED REASON METHOD EXHIBIT C - INSTRUCTIONS Sa 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)

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

E - OPERATOR 1 RAINING + !! CENSE EXAMINATION F F - ADMINISTRATIVE (5)

G OPERATIONAL ERROR (EXPLAIN)

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

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE JUNE 15, 1993 REPORT MONTH MAY, 1993 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 SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO ,

NO. DATE (1) (HOURS) ; (2) , REACTOR (3) REPORT # (4) (5) PREVENT RECURRENCE ,

4 12 930507 5 44.0 H 4 N/A HC HTEXCH WATERBOX CLEANINO REACTOR NOT SHUTDOWN

. 13 930509 F 6.0 H 4 N/A IF INSTRU TIP KACHINE MAINTENANCE REACTOR NOT SHUTDOWN 14 930524 F 38.0 A 4 N/A CH PUM0XX REACTOR TEED PUMP MAINTENANCE REACTOR NOT SHUTDOWN f

88.0

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

F FORCED . REASON NETH00 EXHlBIT C - INSTRUCTIONS S - SCHEDULED A EQUIPMENT FAILURE (EXvlAIN) 1 - MANUAL FDR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER)

D - REGULt. TORY RESTRICTION 4 - OTHER (EXPLAIN) FILE (NUREG-0161) ,

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

C - OPERATIONAL ERROR (EXPLAIN)

H - DTHER(EXPLAIN). EXHIBIT I - SAME SOURCE I

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