ML20029C642

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Monthly Operating Repts for Mar 1994 for Peach Bottom Units 2 & 3.W/940412 Ltr
ML20029C642
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/31/1994
From: Jeffrey W, Rainey G
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CCN-94-14053, NUDOCS 9404200295
Download: ML20029C642 (13)
v • d • e


Text

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Osritj R. Milney .

' Vice President .

Peach Bottom Atomic Power Station

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PECO ENERGY- gcoglgc Delta. PA 17314-9739 -

717 456 7014 April 12,1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 j

Docket Nos. 50-277 and 50-278 Gentlemen:

Enclosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of March 1994 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regutatory Guide 10.1,' Revision 4.

Sincerely, J-

/

Gerald R. Rainey Vice President 4%~(gpf +

GRR/AJW/0HG/TJN/MSH:wjj ,

enclosures cc: R.A. Burricelli, Public Service Electric & Gas

~ W.P Domsife, Commonwealth of Pennsylvania R.I. McLean, State of Maryland T.T. Martin, Administrator, Region 1. USNRC W.L Schmidt, USNRC, Senior Resident inspector H.C. Schwemm, Atlantic Electric .

C.D. Schaefer, Delmarva Power INPO Records Center '

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4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE APRIL 7,1994 REPORT MONTH MARCH, 1994 COMPLETED BY PECO ENERGY COMPANY W. J. JEFFREY PERFORMANCE AND RELIABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATICW TELEPHONE (717) 456 7014 EXT. 4027 MEfH00 0F LICENSEE SYSTEM CCNPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO. DATE (1) (H0liRS) (2) REACTOR (3) REPORT # (4) (5) PREVENT RECURRENCE (1) (2) (3) (4)

F FORCED REA$0N METHOD EXHIBIT G -INSTRUCTIONS :i

$

  • SCHEDULED A EQUIPMENT FAILURE (EXPLAIN) ~

1

  • MANUAL FOR PREPARATION OF DATA B MAINTENANCE OR TEST 2 MANUAL SCRAM. ENTRT SHEETS FOR LICENSEE 'I C - REFUELING 3 AUTCHATIC SCRAM. EVENT REPORT (LER) .]

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

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

G OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAIN) EXHIBIT I SAME SOURCE  ;

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PEACH BOTTOM ATOMIC POWER STATION NRC MONTHLY OPERATIONS

SUMMARY

MARCH 1994 OVERVIEW OF ACTIVITIES

.QOMMON PLANT The following plant maintenance outages occurred during the month of March

On March 4,1994 at 04:00 hours power was reduced to perform turbine control valve testing. The unit was returned to 100% power at 07:00 hours.

On March 13,1994 at 01:00 hours power was reduced to perform a rod pattern adjustment. The unit was returned to 100% power at 16:00 hours.

On March 25,1994 at 04:00 hours power was reduced to perform a symmetric rod pattern adjustment and calibrate the LPRM. Power was returning to 100% on March 26,1994 but at 18:00 hours power was reduced again to perform another rod pattern adjustment.

On March 27,1994 at 13:00 hours the unit reached 100% nominal power and remained at that level for the rest of March.

The following maintenance outages occurred on Unit 2:

  • SBLC Pump 'B' Mill T_a Unit 3 began the month of March at a nominal 100% power and operated at that level for the rest of the month The following maintenance outages occurred on Unit 3:
  • CAC Drywell Sample Valve

.. Docket No. 50 277 -

,- Attachm:nt to Monthly Operating Report for March 1994 UNIT 2 REFUELING INFORMATION

1. .Name of facility:

Peach Bottom Unit 2

2. Scheduled date for next refueling shutdown:

Reload to scheduled for September 17,1994.

3. Scheduled date for restart following refueling:

Restart following refueling forecast for November 12,1994.

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

Yes. -

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

93-01 ARTS /MELLA 9342 Recirc Pump M/G Set Replacement .

9312 Power Rerate 94-01 ECCS Refuel Operability Requirements 9214 - Unit 2 CAD Analyzer Upgrade

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

9341 Submitted April 1993 9312 Submitted June 1993 -:

92-14 Scheduled May 1994 93-02 -Scheduled May 1994 94-01. Scheduled May 1994

. .* :2

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-

- Docket No. 50-277 Attachment to Monthly Operating Report for March 1994 Page 2 UNIT 2 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 Assemblies (b) Fuel Pool - 2164 Fuel Assemblies,58 Fuel Rods

8. The present licer. sed 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 2002 without full core offload capability.

September 1998 with full core offload capability.

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Docket No. 50-278 Anachrnent to Monthly Operating

  • - Report for March 1994 UNIT 3 REFUELING INFORMATION
1. Name of facility:

Peach Bottom Unit 3

2. Scheduled date for next refueling shutdown:

Reload 10 scheduled for September 11,1995

3. Scheduled date for restart following refueling Restart following refueling scheduled for November 13,1995
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. Schet 3d 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 procedures:

N/A

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

(a) . Core - 764 Fuel Assemblies (b) Fuel Pool 2201 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.

.____.x . .:. .

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8 AVERAGE DA!LY UNIT POWER LEVEL DOCKET NO. 50 277 UNIT PEACH BOTTOM UNIT 2 DATE APRIL 7,1994 COMPANY PECO ENERGY COMPANY W. J. JEFFREY PERFORMANCE AND RELIABILITY SITE ENGINEER!NO PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456 7014 EXT, 4027 MONTH MARCH 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE NET) (MWE NET) 1 1062 17 1061 2 1065 18 1061 3 1065 19 1068 4 1062 20 1060 5 1061 21 1068 6 1065 22 1063 7 1065 23 1059

8. 1061 24 1063 9 1057 25 1013 10 1028 26 978 11 1053 27 1020 12 1049 28 1060

'f 13 1006 29 1068 14 1058 30 1055 15 1058 31 1058 16 1054 1

i AVERAGE DA!LY UNIT POWER LEVEL DOCKET No. 50 278 UNIT PEACH BOTTOM UNIT 3 DATE APRIL 7,1994 COMPANY PECO ENERGY COMPANY W. J. JEFFREY PERFORMANCE AND RELIABILITY

$1TE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027 MONTH MARCH 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWE-NET) (MWE-NET) 1 1069 17 1065 2 1068 18 1061 3 1072 19 1065 4 1064 20 1057 5 1069 21 1061 6 1065 22 1056 7 1069 23 1061 8 1069 24 1057 9 1065 25 1073 ,

10 1013 26 1070 11 1060 27 1053 12 1065 28 1052 13 1057 29 1052 14 1065 30 1056 15 1061 31 1055 16 1056

  • , OPERATING DATA REPORT DOCKET No. 50 277 DATE APRIL 7,1994 COMPLETED BY PECO ENERGY COMPANY W. J. JEFFREY-PERFORMANCE AND RELIABILITY

$1TE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT, 4027 OPERATING STATUS

1. UNIT NAME: PEACH BOTTOM UNIT 2 NOTES:
2. REPORTING PERIOD: MARCH, 1994
3. LICENSED THERMAL POWER (MWT): 3293
4. NAMEPLATE RATING (GROSS MVE): 1152
5. DESIGN ELECTRICAL RATING (NET MWE): 1065
6. HAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1051
8. If CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744 - 2,160 173,040
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 2,160.0 '108,272.1
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON LINE 744.0 2,160.0 104,380.2
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 2,422,613 6,800,722 311,290,215
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 806,000 2,244,100 102,395,590
18. NET ELECTRICAL ENERGY GENERATED (MWh) 2,179,913 98,170,715

.....'782,974 PAGE 1 0F 2

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  • OPERATING DATA REPORT (CONTINUED) DOCKET No. 50 - 277 DATE APRIL 7,1994 THIS MONTH YR T0*DATE CUMULATIVE
19. UNIT SERVICI FACTOR 100.0 100.0 60.3
20. UNIT AVAILABILITY FACTOR 100.0 100.0 60.3
21. UNIT CAPACITY FACTOR (USING MDC NET) 100.1 96.1 54.0
22. UNIT CAPACITY FACTOR (USING DER NET) 98.8 94.8 53.3
23. UNIT FORCED OUTAGE RATE 0.0 0.0 13.6
24. SHUTDOWNS $CHEDULED DVER NEXT 6 MONTHS (TTPE, DATE, AND DURATION OF EACH):
25. IF SHUTDOWN AT END OF REPORT PER100, EST! MATED DATE OF STARTUP: N/A
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 COMMERCIAL OPERATION 07/05/74 t

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e i OPERATING DATA REPORT DOCKET NO. 50 278 DATE APRIL 7,1994

' COMPLETED BY PECO ENERGY COMPANY W. J. JEFFREY PERFORMANCE AND RELIABILITY-SITE ENGINEERING t PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456 7014 EXT. 4027 OPERATING STATUS

1. UNIT NAME: PEACH BOTTOM UNIT 3 NOTES:
2. REPORTING PERIDO: MARCH, 1994
3. LICENSED THERMAL POWER (MVT): 3293
4. NAMEPLATE RATING (CROSS MWE): 1152
5. DESIGN ELECTRICAL RATING (NET MVE): 1065
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
7. MAXIMUM DEPENDABLE CAPACITY (NET MVE): 1035
8. IF CHANGES OCCUR IN CAPAC!TY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS HONTH YR TO-DATE CUMULATIVE

11. HOURS IN REPORTING PCR100 744 . 2,160 168,936
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 2,079.0 106,750.4
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 O.0 0.0
14. HOURS GENERATOR ON LINE 744.0 2,0 79.0 103,370.2
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 2,447,566- .6,812,662 305,586,139 ,
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 809,200 2,258,600 100,248,732 >
18. NET ELECTRICAL ENERGY GENERATED (MWH) 789,091 2,198,853: 96,172,860 PAGE 1 OF 2 t

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  • OPERATING DATA REPORT (CONTINUED)

, DOCKET No. 5,0 - 278 DATE APRIL 7,1994 THIS MONTH YR*TO DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 96.3 61.2
20. UNIT AVAILABILITY FACTOR 100.0 96.3 61.2.
21. UNIT CAPACITY FACTOR (USING MOC NET) 102.5 98.4 55.0
22. UNIT CAPACITY FACTOR (US!kG DER NET) 99.6 95.6 53.5
23. UNIT FORCED OUTAGE RATE 0.0 3.8 12.2
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 11/14/95
26. UNITS IN TEST STATUS (PRIOR TO CCHMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 COMMERCIAL OPERAfl0N 12/23/74 O

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l UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 277

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UNIT NAME PEACH BOTTOM UNIT 2 DATE APRIL 7,1994 REPORT MONTH MARCH, 1994 COMPLETED BY PECO ENERGY COMPANY W. J. JEFFREY PERFORMANCE AND RELIABILITY

$1TE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456 7014 EXT. 4027 l NETH00 0F LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATIONjREASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO. DATE i (1); (HOURS)l (2) REACTOR (3) REPORT # (4) (5) PREVENT RECURRENCE 13 940304 S 3.0 B 4 N/A HA VALVEX TURBINE STOP VALVE TESTING. REACTOR NOT SHUTDOWN 14 940313 S 15.0 H 4 N/A RC CONROD R00 PATTERN ADJUSTMENT. REACTOR NOT SHUTDOWN.

15 940325 S 38.0 H 4 N/A RC CONROD SYMMETRIC ROD PATTERN ADJUSTMENT AND LPRM CALIBRATION 16 940326 7 19.0 M 4 N/A RC CONROD ROD PATTERN ADJUSTMENT REACTOR NOT SHUTDOWN T5.0 (1) (2) (3) (4)

F - FORCED REASON METHOD EXHIBIT G INSTRUCTIONS

$ SCHEDULED A EQUIP > ENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA 8 - MAINTEhANCE OR TEST 2

  • MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C REFUELING 3.- AUTOMATIC SCRAM. EVENT REPORT (LER) 0 - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN) FILE (NUREG 0161)

E OPCRATOR TRA!NING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)

G - OPERATIONAL ERR 7R (EXPLAIN)

Ha OTHER(EXPLAIN) EXHIBIT I SAME SOURCE

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