ML20064E654

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Monthly Operating Repts for Jan 1994 for Peach Bottom Atomic Power Station Units 1 & 2
ML20064E654
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 01/31/1994
From: Jeffrey W, Rainey G
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9403140397
Download: ML20064E654 (14)


Text

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Certid R. Rijnsy V co President Peach Dottom Atomic Power Station 4

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Delta. PA 17314-9739 717 456 7014 February 14,1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 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 January 1994 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Sincerely, Gerald R. Rainey Vice President

/$ ff,4b GRR/AJW/GHG/TJN/MSH:wjj enclosures cc:

R.A. Burricelli, Public Service Electric & Gas W.P. Dornsife, Commonwealth of Pennsylvania R.I. McLean, State of Maryland T.T. Martin, Administrator, Region I, USNRC W.L Schmidt, USNRC, Senior Resident inspector H.C. Schwemm, Atlantic Electric C.D. Schaefer, Delmarva Power INPO Records Center l

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ccn #94-14021 1,1005 940314o397 94o1s1 f

PDR ADDCK 05000277 i

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f PEACH BOTTOM ATOMIC POWER STATION NRC MONTHLY OPERATIONS

SUMMARY

JANUARY 1994 OVEPYlEW Or ACTIVITIES

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QQMMON Pl. ANT The following plant maintenance outages occurred during the month of 0<tcember.

  • #2 Start-up Transformer UNIT R Unit 2 Segan the month of December at a nominal 100% power.

Cn January 2,1994 at 05:00 hours power was reduced to perform a rod pattern adjustment. The unit was returned to 100% power at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />.

On January 5,1994 at 03:00 hours power was reduced to 65% due to problems with the "5A* heater extraction valve. The unit was returning to 100% power but was held at 73% to perform condensate demineralizer regeneration.

On January 7,1994 at 12:00 hours the unit was returned to 100% nominal power.

On January 8,1994 at 01:00 hours power was reduced to perform rod pattern adjustments. The unit was returning to 100% but at 18:00 hours power was held due to problems with "A" reactor feed pump.

On January 10,1994 at 12:00 hours the unit was retumed to 100% nominal power.

On January 29,1994 at 01:00 hours ' power was reduced to perform rod pattern adjustments.

On January 30,1994 the unit was returned to 100% nominal power and operated at that level for the remainder of January.

The following maintenance outages occurred on Unit 2:

  • "A" Loop RHR UNIT 3 Unit 3 began the month of January at a nominal 100% power and operated at that level for the entire month.

The following maintenance outages occurred on Unit 3:

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Docket No. 50-277 Attachment to Monthly Operating 7

Report for January 1994

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UNIT 2 REFILELING INFORMATION 1.

Name of facility:

e 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 November 8,1994.

Will refueling or resumption of operation therefore require a technical specification change or other 4.

license amendment?

No.

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

Scheduled date(s) for subm!tting proposed licensing action and supporting information:

5.

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 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 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.

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i-t Docket No. 50-277 Attachment to Monthly Operating r

Report for January 1994 Page 2

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!) NIT 2 REFUELING INFORMATION (Continued) 9.

The projected date of the last refueling that can be discharged to the spent fue! pool assuming the present capacity:

September 2002 without full core offload capabildy.

September 1998 with full core offload capabiltty.

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Docket No. 50-278 Attachment to Monthly Operating Report for January 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.

Wiii 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?

o heduled date(s) for submftting proposed licensing action and supporting information:

5.

c 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 assemblies (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.

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Docket No. 50 278 Attachment to Monthly Operating Report for January 1994 Page 2 t)]{D_3_BFJ_QELING INFORMATION (Continued) 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assurning the present capacity:

September 2003 without full core offload capability.

September 1997 with full core offload capability.

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r AVERAGE DAILY UNIT POVER LEVEL 4

1 DUCKE1 No. 50 277 j

UNIT PEACH BOTTOM UNIT 2 k

OATE FhBRUARY

'v94 COMPANY PECO ENERGY COMPANY W. J. JEFFREY PERFORMANCE & RELIABILITY SITE ENG!hEERitG PEACH B0f f 0H ATOMIC POWER STATION

?ELEPHOhE (717) 456 7014 EXT. 4027 MONTH JANUARY 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEV'i (MWE* NET)

(MWE-kET) 1 1056 17 1057 2

1021 18 1052 3

1070 19 1065 4

1062 20 1056 5

826 21 1060 6

993 22 1057 7

1041 23 1052 8

855 24 1056 9

921 25 1060 10 1018 26 1040 11 1057 27 1052 12 1061 28 1052 13 1057 29 831 14 1057 30 1044 15 1057 31 1070 16 1061 i

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AVERAGE dally UNIT POWER LEVEL' a

0;cKE1 43. 50 27C UNIT PEACH B01TO4 l' NIT 3 4.........

DATE FEBRUARY 11,1994 COMPANY PECO ENERGY COMPANY W. J. JEFFREY PERFORMANCE & RELIABILITY SITE ENGINEERING PEACH BOTTON ATOMIC POWER STATION TELEPHONE (717) 456 7014 EXT, 4027 l

MONTH JANUARY 1994 DAY AVERAGE DAILY 00WER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE NET) 1 1065 17 1065 2

1070 18 1069 3

1069 19 1065 4

1069 20 1065 5

1062 21 1069 6

1062 22 1070 7

1069 23 1070 8

1069 24 1069 9

1069 e

25 1069 10 1061 26 1070 11 1065 27 1065 12 1065 28 1074 13 1065 29 1070 14 1065 30 1070 15 1069 31 1068 16 1061 i

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OPERATING DATA REPORT DDCKT1 ho. 50 - 777 DATE FEBRUARY 11,1994 COMPLETED BY PECO ENERGY COMPANY W. J. JEFFREY PERf0RMANCE & REllABILITY SITE ENGINEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456-7014 EXT. 4027 OPERATING STATUS

1. UNIT NAME: 'eACH 30TTOM UNIT 2 NG'ES:

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?. REP 0kitNG '?R100:

JANUARY, 1994

3. LICENSED Tet RMAL 8 CWER(MWT):

3293

4. NAMEPLATE RATING (GROSS MW-):

1152

5. DESIGN ELECTRICAL RATING (NET MWE):

1065

6. MAXIMUM DEPENDABLE CAPACITY (CROSS MWE) b98
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

b5h

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 (kET MWE):
10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO DATE CUMULATIVE f

11. HOURS IN REPCRTING PERIOD 744 744 171,624
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 744.0 106,856.1
13. PEACTOR RESERVE SHUTDOWN HOURS b$b b$b b$b
14. HOURS GENERATOR ON LINE h45b hA2b kb2,bbE$2
15. UNIT RESERVE SHUTDOWN HOURS bb bb b$b
16. GROSS THERMAL ENERGY GENERATED (MWH) 2,375,242 2,375,242 306,864,735
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) hbk[bbb hbk,bbb kbb,935,h9b
18. NET ELECTRICAL ENERGY PENERATED (MWH) 762,627 762,627 96,753,429 PAGE 1 OF 2

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l OPERATINO DATA REPORT (CONTINUED) '.

DOCKET' NO. 50 - 277 p

DATE FEBRUARY 11,1994 ii!!? h0 NTH 70-TO-DATF CUMULATikk

19. UNIT SC%> ICE TACTOR 100.G

'100.0-59.8 i

20. UN!Y AVAIL %eILITY FACTOR 100.0 100.0-59.8
21. UNIT CAPACITY FACTOR (U5iA1 MDC NET) 97.3 97.3 53.2
22. UNIT CAPACITY FAL'iR (USING LEP NET) 96.4 vb.4 52.7
23. UNIT FORCED OUTAGE Rr,iE 0.0 0.0 13.0
24. SHUTDOWNS SCHEDULEO OVER bEi1 6 ADNTHS (TYrt., 11 ATE, AND DURATION OF EACH):
25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF ST ARTUP: N/A
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICAllTY 09/16/73 INITIAL ELECTRICITY 02/18/74 COMMERCIAL OPERATION 07/05/74 f

PAGE 2 OF 2

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OPERATING DATA REPORT

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.N).FY No. 50 778

.f 44TE FEBRUART 11,1994 COMPLETED BY PtCO ENEE0Y CONFA4!

I W. J..'EF FREY PERFORN.%'CE & RELI ABIL!)Y SITE ENGah'ERING PEACH BOTTO4 ATOMll. POWER STA' ION TEd ?MONE (717) '.56-7V.'. EXT. 4027 OPERATING STATUS

1. UNIT NAME: PEACH BOTTOM UNIT 3 iTorES:
2. REPORTING PERIOD:

JANUARY, 1994 LICENSED THERMAL POWER (MWT):

3293

4. ;4MEPLATE RATING (CROSS MWE):

1152 5.DESIGNELECTRICALRATING(NETMWE)$

1065 e

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6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098
7. MAX 1 HUM DEPENDABLE CAPACITY (NET MWE):

1035 l

8. IF CHANGES GCCUR 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 RESTRICil0NS, IF ANY:

THl$ MONTH YR-TO-DATE CUMULATIVE 4

11. HOURS IN REPORTING PERIOD 744 744 167,520
12. NUMBER OF HOURS REACTOR WAS CRITICAL 744. 0 744.0 105,415.4
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 744.0 744.0 102,035.2
15. UNIT RESERY

.UTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMA ENERGY GENERATED (MWH) 2,447,700 2,447,700 301,221,177
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 816,800 816,800 98,806,932
18. NET ELECTRICAL ENERGY GENERATED (MWM) 794,010 794,010 94,768,346 PAGE 1 0F 2

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' OPERATING DATA REPORT (CDNilNUED)..

00CKET'No. 50 278 DATE FEBRUARY 11,1994 lHIS MONTH YR-TO DATE CUMULATI.'k

19. UN!T SERVICE FACTOR 100.0 100.0 60.7
20. UNIT AVAILABILITY FACTOR 100.0 100.0 60.7
21. UNIT CAPACITY FACTOR (USING MCC NET) 103.1 1CT 1 54.4
22. l' NIT CAPACITi rACTOR (USING DER NET) 100.2 100.'c

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23. UNIT FORCED 00'.tcr RATE 0.0 0.0 12.3 24 $HUTDOWNS $CHEDULLD OVER NEXT 6 MONTHS (iYPE, DATE, AND DURAi!ON OF EACH);
25. IF "WUTDOWN AT END OF REPORT PERIDO ESilMATED DATE OF STARTUP: 11/14/95
26. UN!!S IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 COMMERCIAL OPERATION 12/23/74 e

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UNIT SHUTDOWNS AND FCVER REDUCTIONS DOCKET ko. !b 2(f UWIT NAME PEALS '.1TTid UNIT 2 DATE FEBRUAR.' 11,1994 REPORT V9 NTH JANUARY, 1994 COMPLETED BY PECO ENERGY 8.1MPANY e

W. J. JEFFREY PERFORMANCE & RE! ' A*.f LITY SITE ENGTP*ERING PEACH BC#1(A ATOMIC POLCR C'.'T!ON TELEPHONE (717) 456-1014 EXT. 4027 l

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METHOD B LICENSEE SYSTEM. COMPONENT CAUSE AND CORRECTIVE lTYPEjDURATION} REASON SHUTTING DOWN EVENT CODE CODE ACTION TO No.

DATE l (1)l (HOURS)l (2)

REACTOR (3) l

ORT #

(4)

(5)

PREVENT RECURRENCE i

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12.0 N

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N/A l RC CONROD ROD PATTERN ADJUSTMENT. REACTOR NOT SHUTCOWN 02 940105 7

22.0 A l 4

N/A CH l VALVEX SA HEATER EXTRACTION VALVE PROBLFMS l

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REACTOR NOT SHUTDOWN i

03 940106 F

35.0 A

4 W/A WC CEMINX CONDENSATE DEMIN REGENERATION.

REACTOR NOT SHUT 00WN 04 940108 l S 17.0 l H

N/A RC CONR00 ROD PATTERN ADJUSTMENT. REACTOR NOT SHUT 00WN l

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05 940108 5

42.0 j B l 4

  • l N/A CH PUNPXX A REACTOR FEED PUMP MAINTENANCE.

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06 940113 S

3.0 fB 4

N/A HA VALVEX TURBINE STOP VALVE TESTING. REACTOR NOT l

SHUTDOWN I

07 940123

$l 4.0 l B

4 l

N/A

' HA VALVEX TURBINE STOP VALVE TESTING. REACTOR NOT l

l SHUTDOWN i,

h 08 940129, S 39.0 H

4 N/A RC CONR00-R00 PATTERN ADJUSTMENT. REACTOR NOT SFUTOCbN l

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(3)

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F tO9CED REASON METH00 EXHIBli G - INSTRUCTIONS S

"l' EDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DA?A B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SHEETS FOR LICENC.'E C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EAPLAIN)

FILE (NUREG-0161)

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  • OPERATOR TRAINING + LICENSE EXAMINATION F - ADMIN!$TRATIVE (5)

G - OPERATIONAL ERROR (EXPLAlk)

H - OTHER(EXPLAIN)

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'JIIT SHOTDDWNS A: P POWER REDUCTIDHs DOCKET No. 50 278 UNIT NAME PEACH BOTTOM UNIT.'s

-l DATE FEBRUARY 11,1994 REPOR1 FONTH JANUAR), 1994 COMPLETED BY PECO ENERGY COMPANY W. J. JEFFREY i

PERFORMANCE & RELIABILITY I

SITE ENG!hEERING PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 456 7014 EXT, 4027 l

l METHOD OF i LICENSEE l SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE lDURATIONjREASON SHUTTING DOWNf EVENTl CODE CODE ACTION TO No.

DATE (1)l (HOURS)l (2)

REACTOR (3) l REPORT # l (4)

(S)

PREVENT RECURRENCE I

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(2)

(3)

(4)

F FORCED REASON METH00 EXHIBli G - INSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA i

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 (5)

G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAIN)

EXHIBli 1 - SAME SOURCE e

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