ML20246P762

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Monthly Operating Repts for June 1989 for Peach Bottom Atomic Power Station Units 2 & 3
ML20246P762
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 06/30/1989
From: Baron M, Danni Smith
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8907200305
Download: ML20246P762 (14)
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+- PHILADELPHU PLECTRIC COMPANY PEACII BOTIOM ATOMIC POWER STATION R. D. I. Box 208

. Delta, Pennsylvania 17314 E nacu sernm-Tusworn or sxcru.cace (717) 456-7014 D. M. Smith '

Vice President July 14, 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 Gentlemen:

Ennosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of June,1989 fenvarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Sincerely, use h~ &

DMS/MJB: cmc TW Enclosure ec: 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 l

CNe9.NRC 8907200305 890630 PDR ADOCK 05000277 ,

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u NRC Monthly Operations Summary Peach Bottom Atomic Power Station

f3 ' June 1989 pO

" UNIT 2 The unit began the month in the "run" mode at 33% power and 2.0 MWe, The Power Ascension prograu continued throughout the month. Scram time testing of control rods was completed and several back-shift power

~ best changes were completed for cold li;.:nse operator training. A planned turbine trip from 18% power was performed to demonstrate plant response; a high voltage fuse on the voltage regulator potential transformer was

. replaced after the tdp. The unit ended the month at 68% power and 700 MWe.

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

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i CC0689.NRC Q L -- _- _

l Docket No. 50-277 l'

Attachment to Monthly Operating Report for June 1989 UNIT 2 REFUELING INFORMATION

1. Name of facility:

Peach Bottom Unit 2

2. Scheduled date for next refueling shutdown:

(1) Reload 7 completed (2) Reload 8 scheduled for January 6,1991

3. Scheduled date for restart following refueling-(1) Completion of Power Ascension and Operator training targeted for mid-August 1989.

(2) Restart following refueling scheduled for April 6,1991

4. Will refueling or resumption of operation therefore require a technical specification change or oth'er 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:

Nct applicabic.

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:

Refueling completed.

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

(a) Core - 764 Fuel Assemblics (b) Fucl Pool - 1734 Fuel Assemblics,58 Fuel Rods CC0689.NRC a

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Docket No. 50-277 Attachment to Monthly Operating Report for June 1989 Page 2 UNIT 2 REFUELING INFORMATION (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 relicensed for 3819 fuel assemblics.

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

September 2003 without full core offload capability.

September 1997 with full core offload capability.

sh CC0(.89.NRC

Docket No. 50-278 Attachment to Monthly Operating Report for June 1989 UNIT 3 REFUELING INFORMATION

1. Name of facility:

Peach Bottom Unit 3

2. Sci.eduled date for next refueling shutdown:

(1) Reload 7 in progress (2) Reload 8 scheduled for August 31,1991

3. Scheduled date for restart following refueling (1) Restart following refueling scheduled for September 30,1989 (2) Restart following refueling scheduled for October 29,1991 4 Will refueling or resumption of operation thereafter require a technical specification change or other license tunendment?

Yes.

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

(1) Cycle 8 Reload Amendment (2) Minimum SRM Count Amendment

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

(1) Cycle 8 Reload License Amendment submitted July 1988 (2) Minimum SRM Count Amendment submitted December 1988

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 dcalen, new operating procedures:

1 None expected.

CCOWLNRC

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l Docket No. 50-278 Attachment to Monthly Operating Report for June 1989 Page 2 UNIT 3 REFUELING INFORMATION (Continued)

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

(a) Cme - 0 Fuel Assemblics (764 assemblics offloaded during outage)

(b) Fuel Pool- 2260 Fuel Assemblics,6 Fuel Rods l

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 assemblies. This modification began on February 20,1987. The completion date for this modification has been rescheduled for the first quarte: of 1990 to accommodate the Unit 3 outage.

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 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 rcracking modification):

September 20N without full core offload capability.

September 1998 with full core offload capability. l l

CCW29.NRC

AVERAGE DAILY UNIT POWER LEVEL 00CKET NO. 50 - 277 UNIT PEACH BOTTOM UNIT 2 CATE JULY 15, 1989 COMPANY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 457-7014 EXT. 3321 MONTH JUNE 1989 CAY AVERAGE DA!LY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET) (MWE-NET) 1 251 17 269 2 257 18 226 3 25'5 19 69 4 249 20 178' 5 259 21 270 -

6 256 22 265 7 261 23 269 8 256 24 271 9 262 25 271 10 264 26 269 11 269 27 265 12 258 28 290 13 266 29 390 14 262 30 348 15 270 16 269 I

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- AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 278 1

UNIT PEACH BOTTOM UNIT 3 CATE JULY 15, 1989 COMPANY PHILADELPHIA ELECTRIC COMPANY M. J, BARON SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 457-7014 EXT, 3321 HONTH JUNE 1989 DAY AVERAGE DAILY POWER LEVEL DAY . AVERAGE DAILY POWER LEVEL (HWE-NET) (MWE-NET) 1 0' 17 0 2 0 18 0-3 0 19 0 4 0 20 0 5 0 21 0 -

6 0 22 0 7 0 23 0 6 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 16 0 i

OPERATING DATA REPORT i

l DOCKET NO. 50 - 277 DATE JULY 15, 1989 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 457-7014 EXT. 3321 OPERATING STATUS

1. UNIT NAME: PEACH BOTTOM UNIT 2 NOTES: UNIT 2 IN POWER ASCENSION
2. REPORTING PERICO: JUNE. 1989 AS OF APRIL 26, 1989 1
3. LICENSED THERMAL POWER (MWT): 3293
4. NAMEPLATE RATING (GROSS MWE): 1152
5. DESIGN ELECTRICAL RATING (NET MWE): 1065
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1051
8. If CHANGES DCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:
9. POVER LEVEL TO WHICH RESTRICTED. IF ANY (NET MWE):
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CUMULAT!VE

11. HOURS IN REPORi!NG PERlr 720 4,343 131,399
12. NUM8ER OF HOURS REACTOR WAS CRITICAL 720.0 1,358.9 75,555.7
13. REACTOR RESERVE SHUT 00VN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 704.6 885.5 72,712.3
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 759.336 922,704 213,733.449 1 '4ROSS ELECTRICAL ENERGY GENERATED (MWH) 201,090 235,560 70.254.790
18. NET ELECTRICAL ENERGY GENERATED (MVH) 187,607 196,800 67,188.916 PAGE 1 CF 2 l

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OPERATING DATA REPORT (CONTINUED) DOCKET NO. 50 - 277 DATE JULY 15, 1989 THIS HONTH YR-TD-DATE CUMULATIVE

.t9, UNIT SERVICE FACTOR 97.9 20.4 55.4

'20. UNIT AVAILABILITY FACTOR 97.9 20.4 55.4

21. UNIT CAPACITY FACTOR (USING MDC NET) 24.8 4.3 48.7 22 UNIT CAPACITY FACTOR (USING DER NET) 24.5 - 4.3 - 48.0
23. UNIT FORCED OUTAGE RATE 2.1 6.5 14.6
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):

REFUELING OUTAGE

25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 INIT]AL ELECTRICITY 02/18/74 COMMERCIAL OPERATION 07/05/74 -

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OPERATING DATA REPORT DOCKET NO. 50 - 278 DATE JULY 15, 1989 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVISOR ,

REP 03TS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 457-7014 EXT. 3321 OPERATING STATUS

1. UNIT NAME: PEACH BOTTOM UNIT 3 NOTES: UNIT 3 REMAINED SHUT DOWN 2, REPORTING PERIOD: JUNE. 1989 VITH MODIFICATION
3. LICENSED THERMAL POWER (MWT): 3293 ACTIVITIES IN PROGRESS.
4. NAMEPLATE RATING (GROSS MWE): 1152
5. DESIGN ELECTRICAL RATING (NET MWE): 1065
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1035
8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) $!NCE LAST REPORT, GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
10. REASONS FOR RESTRICTIONS, IF ANY: .

THIS MONTH YR-TO-0 ATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720 4,343 127,295
12. NUMBER OF HOURS REACTOR WAS CRITICAL 0 0 76,357.4
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GEWERATOR ON-LINE 0.0 0.0 73,929.3
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 0 0 215.278,901
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0 0 70,611,432
18. NET ELECTRICAL ENERGY GENERATED (MWH) -2,613 -23,909 67,627,246 i

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OPERATING DATA REPORT (CONTINUED) DOCKET JJ. 50 - 278

'DATE JULY 15, 1989 THIS MONTH YR-TCr-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 0.0 0.0 58.1
20. UNIT AVAILABILITY FACTOR 0.0 0.0 58.1
21. UNIT CAPACITY FACTOR (USING MDC NET) 0,0 0.0 51.3
22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 49.9
23. UNIT FORCED OUTAGE RATE 0.0 0.0 13.3
24. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH).
25. IF SHUTDOWN AT IND OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: September 30, 1989
26. . UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 COMMERCIAL OPERATION 12/23/74 PAGE 2 0F 2

l UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 277 UNIT NAME PEACH BOTTOM UNIT 2 OATE JULY 15, 1989 l REPORT MONTH JUNE. 1989 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY H, J. BARON SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 457-7014 EXT. 3321 HETHC0 0F LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE OURATTON REASON SHUTTING DOWN IVENT CODE CODE ACTION TO NO. DATE (1) (HOURS) (2) REACTOR (3) EPORT f (4) (5) PREVENT RECURRENCE 2 89061B F 000.0 A 4 (Note 1) N/A EB CKTBRK GENERATOR AUTOMATIC VOLTAGE REGULATOR POTENTIAL TRANSFORMER FUSE BLEW 3 890619 F 015.4 A 4 (Note 1) N/A EB CKTBRK REPLACE FUSE IN POTENTIAL TRANSFORMER 4 890630 S 000.0 B 4 (Note 1) N/A CH PUMPXX REACTOR FEED PUMP POWER ASCENSION TESTING

- 15.4 (1) (2) (3) (4)

F - FORCED 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 - REFUELhNG 3 - AUTOMATIC SCRAM. EVENT REPORT (LER)

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

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

G - OPERATIONAL ERROR (EXPLAIN)

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

i Note 1: Power reduction only. Reactor was not shut down.

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t UNIT SHUTOOWNS AND PGVER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE JULY 15, 1989 REPOR1 MONTH JUNE, 1989 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 457-7014 EXT. 3321 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING 00WN EVENT- CODE CODE ACTION TO NO. DATE (1) (HOURS) (2) REACTOR (3) REPORT # (4) (S) PREVENT RECURRENCE 7 890601 5 720.0 C l'. N/A RC FUELXX CONTINUATION OF REFUEL OUTAGE 720.0 (1) (2) (3) (4)

F - FORCED 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)

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

E - OPERATOR TRAINING + LICENSE EXAMINATION f - ADMINISTRATIVE (S)

G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAIN) EXHIBIT 1 - SAME SOURCE I

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