ML20207R916

Monthly Operating Repts for Feb 1987

ML20207R916
Person / Time
Site:	Peach Bottom
Issue date:	02/28/1987
From:	Alden W, Middleton L PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8703180298
Download: ML20207R916 (14)

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Peach Bottom Atomic Power Station Narrative Summary of Operating Experience February, 1987 UNIT 2 Unit 2 began the report period operating at approximately 80%-

power to accommodate the replacement of the

'A' Reactor Feedpump (RFP) turbine coupling and-the

'A' RFP minimum flow valve.

Load was recovered on February 3.

On February 3, load was reduced to 700 MWE to remove the

'A' feedwater heater. string from service due to a tube leak on the A-1 feedwater heater.

The A-1 feedwater heater tube bundle and the secondary drain line between the A-1 and A-2 feedwater heater will be replaced during the upcoming refuel outage.

Meanwhile,

[

Unit-2-has-been-limited-to-a-maximum-operating-level of-85% as a result of the unavailability of the

'A' feedwater heater string.

)

On February 7, load was reduced to 300 MWe to accommodate

p condenser waterbox tube leak inspections and repairs in the B-2 waterbox, ano replacement of the recirculation pump M-G set brushes.

Six tube leaks were found and repaired.

Load was I

restored to 85% power on February 9.

p With the exception of four small reductions for various maintenance activities, Unit 2 operated at 85% power for the remainder of the month.

m UNIT 3 Unit 3 maintained full load through February 10.

N On February 11, load was reduced to approximately 63% power to accommodate condenser waterbox tube leak inspections and repairs in the B-2 and C-2 waterboxes.

One leak was repaired and several plugs were tightened.

Load was reduced again on February 13 for additional tube leak inspections.

No new plugs were installed; however, several previously installed plugs were tightened.

Load was recovered on February 18.

On February 21, a brief load reduction was taken for control rod i

pattern adjustment.

Full load was recovered on February 22 and was maintained through the end of the report period.

8703180298 870228 ~

U PDR ADOCK 05000277 7

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. Docket No. 50-277 Attachment to Monthly Operating Report for February, 1987 UNIT 2 REFUELING INFORMATION 1.

Name of facility:

Peach Bottom Unit 2 2.

Scheduled date for next refueling shutdown:

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March 14, 1987 3.

Scheduled-date-for restart-following refueling:

May 23, 1987 i

. ill refueling-or resumption of operation thereafter require a 4.

W technical specification change or other license amendment?

n

'Yes F

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

Technical Specifications to accommodate reload fuel.

Modifications to reactor core operating limits.

5.

Scheduled date(s) for submitting proposed licensing action and

~

. supporting information:

Reload 7 license ar.sndment submitted January 9, 1987.

p 6.

Important licensing considerations associated with refueling, e.g., new or differenc fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel

. design, new operating procedures:

None expected.

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 - 1462 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.

Replacement higher density fuel racks were approved by the NRC on February 19, 1986 which increases the licensed fuel pool capacity to a total of 3819 fuel bundles in each fuel pool.

This modification was completed on November 15, 1986.

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Docket No. 50-277 Attachmont to Monthly Operating Report for February, 1987 Page 2 UNIT 2 REFUELING INFORMATION (Continued)

T 9.

The projected date of the last refueling that can be discharged L

to the spent fuel pool assuming the present capacity, subsequent I

to the completion of the new fuel racks installation:

March, 1998 (March 1995, with reserve full core discharge) i d

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Docket No. 50-278 Attachment to Monthly Operating Report for January, 1987 UNIT 3 REFUELING INFORMATION E

1.

Name of facility:

Peach Bottom Unit 3 2.

Scheduled date for next refueling shutdown:

September 12, 1987 3.

Schedul ed -da t e -f or-r es ta r t-f ollowi ng -refueling :

June 17, 1988 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?

Technical Specifications to accommodate reload fuel.

Modifications to reactor core operating limits.

5.

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

Reload 7 License Amendment to be submitted February 5, 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 design, new operating procedures:

None expected.

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 - 1496 Fuel Assemblies, 6 Fuel Rods

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Docket No. 50-278 Attachment to Monthly Operating Report for February, 1987 Page 2 UNIT 3 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 assemblies.- Replacement _ higher _ density _ fuel racks were approved by the NRC on February 19, 1986 which increases the licensed fuel pool capacity to a total of 3819 fuel bundles in each fuel pool.

This modification began on l

February.20, 1987 and should be completed in mid July, 1987.

3 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity, prior to the completion of the new fuel racks installation:

March, 1993 (September, 1987, with reserve full i

core discharge) 10.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the relicensed capacity, 9

subsequent to the completion of the new fuel racks installation:

March, 1999 (March, 1996, with reserve full core discharge) c i

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AVERAGE DAILY M T POE R LEVEL DOCKET ND. 50 - 277 MT PEACH 80TTON (MIT 2 DATE MARCH 13,1987 CO W ANY PHILADELPHIA ELECTRIC CO W ANY L. L. MIDOLETON TECHNICAL ASSISTANT LICENSING SECTION MJCLEAR SUPPORT DEPARTENT TELEPHOE (215) 841-6374 MONTH...FE8RUARY_1987

)

1 DAY AVERAGE DAILY POE R LEVEL DAY AVERAGE DAILY POER LEVEL (19E-9ET I (M-MT) 1 853 17 845 t

1936 18 858 3

1023 19 888 0

859 20 892 5

942 21 892 6

894 22 898 7

7t1 23 850 8

452 24 725 9

870 25 895 10 889 26 889 11 889 27 892 12 894 28 890

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II 892 10 893 16 844

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AVERAGE DAILY thiIT PotER LEVEL DOCKET NO. 50 - 178 LMIT PEACH BOTTOM LMIT 3 DATE MARCH 16,1987 COMPANY PHILADELPHIA ELECTRIC COW ANY y

L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION MJCLEAR SUPPORT DEPARTIENT d

TELEPH0tE I215) 841-6374 MONTH - FEBRUARY-1987-DAY AVERAGE DAILY POMER LEVEL DAY AVERAGE DAILY PCMER LEVEL I PME-fET)

(PME-tET) t 1

1 1071 17 976 t

1070 18 959 3

1072 19 1033

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4 1071 to 1042

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5 1071

• 1 993 6

1019 22 1u70 7

909 13 1071 A

8 1068 24 1064 9

1069 25 1074 10 1045 26 1068 11 762 27 1070

.a 12 928 to 1069 13 719 14 596 15 584 16 590 l

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OPERATIle DATA REPORT DOCKET W. 50 - 277 DATE MARCH 13,1987 COMPLETED BY PHILADELPHIA ELECTRIC COP 58ANY L. L. MIDDLETON TECl#4ICAL ASSISTANT LICENSING SECTION 84JCLEAR SUPPORT DEPARTPENT TELEPHOPE I2151841-6374 u

OPERATING STATUS s

1. 4341T NAPEI PEACH BOTTOM LMIT t l NOTESI tJ'IT 2 EXPERIENCED ONE l

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to REPORTIls PERIOct_ FMamY,1987 SCHEDULEO-LOAD REOUCTION l

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3. LICENSED THERMAL PONERI)9ff)*

3293 l

APS OPE FORCED LOAD l

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l C. NAfEPLATE RATIts (GROSS DOEls 1152 l

REDUCTION.

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5. DESIGN ELECTRICAL RATING INET 99dE):

1065 l

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6. MAXIMUPt DEPENDABLE CAPACITY IGROSS 19EII 1098 l

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7. MAXIISAt DEPENDABLE CAPACITY IDET PDElt 1051 l

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Q. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS DAJPSER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSt m

9. PONER LEVEL TO NHICH RESTRICTED, IF ANY INET 99Els

10. REASONS FOR RESTRICTIONS, IF ANY:

l THIS MONTH YR-TO-DATE CLMULATIVE

11. HOURS IN REPORTIMis PERIOD 672 1,416 110,928

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12. BASSER OF HOURS REACTOR MAS CRITICAL 672.0 1,416.0 73,883.0

13. REACTOR RESERVE SHUTD0Det HOURS 0.0 0.0 0.0

14. HOURS GENERATOR ON-LISE 672.0 1,416.0 71,558.8

15. t#4IT RESERVE SHUTD0D04 HOLNts 0.0 0.0 0.0 i

16. GROSS THERMAL ENERGY GENERATED titel) 1,821,792 4,130,448 211, % 1,817

17. GROSS ELECTRICAL ENERGY GENERATED (P94H) 597,300 1,368,810 69,739,813

18. PET ELECTRICAL ENERGY GENERATED (P991) 581,459 1,33E,512 66,8E1,372 PAGE 1 0F 2 l

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OPERATIle DATA REPORT (CONTIf4JED)

DOCKET NO. 50 - 277 DATE WJtCH 13,1967 THIS MONTH YR-TD-DATE CLMALATIVE

19. MT SERVICE FACTOR 100.0 100.0 64.5

20. M T AVAILABILITY FACTOR 100.0 100.0 64.5

21. MT CAPACITY FACTOR (USING BWC DET) 82.3 89.5 57.3

22. LMIT CAPACITY FACTOR IUSING DER DET) 81.2 88.4 56.6 f

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23. M T FORCEO QUTAGE RATE 0.0 0.0 13.4

24. SHUTDODNS SCHEDULED DVER PEXT 6 MONTHS ETYPE, DATE, AfG DURATION OF EACH):

r REFUELING OlfTAGE h

MARCH 14, 1987 TO MAY 23, 1987

25. IF SHUTDolet AT EdC OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

26. MTS IN TEST STATUS (PRIOR TO ColetERCIAL OPERATION):

FORECAST ACHIEVED

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INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 CoptERCIAL OPERATION 07/05/74 PAGE 2 OF 1

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OPERATIMB DATA REPORT DOCKET NO. 50 - 178 DATE MARCH 16,1987 ColWLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TEC)MICAL ASSISTANT LICENSING SECTION MJCLEAR SUPPORT DEPART *ENT t

TELEPHOE I2153 841-6374 f

OPERATING STATUS

1. LMIT NAME PEACH BOTTOM IMIT 3 l NOTESS LMIT 3 EXPERIENCE TN0 l

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l 1.~ REPORTING PERIODR-FEBRUARY, 1987 l

SCHEDULED LOAD l

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3. LICENSED THERMAL POERtletTit 3293 l

REDUCTIONS.

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l 4.'NAPEPLATE RATING (GROSS 19Els 1152 l

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5. DESIGN ELECTRICAL RATING (ET NEls 1065 l

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6. MAXIN#1 DEPEl#ABLE CAPACITY (GROSS 194Els 1098 l

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7. MAXIltM DEPENDABLE CAPACITY llET NEll 1035 l

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8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS MASER 3 THROUGH 73 SINCE LAST REPORT, GIVE REASONS:

9. PONER LEVEL TO MHICH RESTRICTED, IF ANY INET M4Els

10. REASONS FOR RESTRICTIONS IF ANY 1

THIS MONTri YR-TO-DATE Ct#ULATIVE

11. HOURS IN REPORTING PERIOD 672 1,416 106,824 12.14ASER OF HOURS REACTOR MAS CAITICAL 672.0 1,317.8 75,850.3

13. REACTOR RESERVE SHUTD0De4 HOURS 0.0 0.0 0.0

14. HOURS GENERATOR ON-LIE 672.0 1,305.8 73,575.5

15. LMIT RESERVE SHUTD0604 HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (1994) 1,027,640 3,761,544 214,281,197

17. GROSS ELECTRICAL ENERGY GENERATED (1981) 669,470 1,244,950 70,300,822

18. NET ELECTRICAL ENERGY GENERATED tlMH) 651,456 1,210,109 67,452,202 PAGE 1 0F 2

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OPERATIls DATA REPORT (CONTIIGJED)

DOCKET ND. 50 - 178 e

DATE MARCH 16,1987 THIS MNITH YR-TO-DATE CLMJLATIVE

19. M T SERVICE FACTOR 100.0 92.2 64.9

20. M T AVAILABILITY FACTOR 100.0 92.2 68.9

21. MT CAPACITY FACiOR (USING IGC DET) 93.7 82.6 61.0

22. MT CAPACITY FACTOR (USING DER DET) 91.0 80.2 59.3

23. LDdIT FORCED OUTAGE RATE 0.0 7.8 8.2 q

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24. SHUTD00445 SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)*

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25. IF SHUTD0Det AT EDW OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt

26. LA4ITS IN TEST STATUS (PRIOR TO COPMERCIAL OPERATION):

FORECAST ACHIEVED

' INITIAL CRITICALITY 06/07/74 INITIAL ELECTRICITY 09/01/74 COP 9ERCIAL OPERATICDI 12/23/74 um 6

PAGE 1 0F 2 3

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e LNIT SHUTDODNS AND POER REDUCTIONS DOCKET NO. 50 - 277 LHIT NAPE PEACH BOTTOM LMIT 2 DATE MARCH 13,1987 g

REPORT HONTH FEBRUARY, 1987 COMPLETED BY FHILADELPHIA ELECTRIC COMPANY b

L. L. MIDDLETOP!

TECHNICAL ASSISTANT LICENSING SECT 7_0N WCLEAR SUPPORT DEPARTMENT TELEPHONE II15) 841-6374 l

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lTYPElDURATIONIREASONISHUTTING DoDNl EVENT l CODE l CODE l ACTION TO No.1 DATE l Illl (HOURS)l t2) l REACTOR 83) l REPORT S l I4) l (5) l PREVENT RECURRENCE

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- FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS

- SCHEDULED A - EQUIPMENT FAILURE IEXPLAIN) 1 - MAWAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MAWAL SCRAM.

ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT ILER)

D - REGULATORY RESTRICTION 4 - OTHER IEXPLAIN)

FILE IWREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE I5)

G - OPERATIONAL ERROR (EXPLAIN)

H - OTHERIEXPLAIN)

EXHIBIT I - SAME SOURCE

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LNIT SHUTDODNS Ale PODER REDUCTIONS DOCKET NO. 50 - 278 LNIT NAME PEACH BOTTOM LNIT 3 it DATE MARCH 16,1987 5

L. L. MIDDLETON TECHNICAL ASSISTANT

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NUCLEAR SUPPORT DEPARTENT 1

TELEPHONE I215) 841-6374 N

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- FORCED REASON MTH00 EXHIBIT G - INSTRUCTIONS T

- SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MAPAJAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT ILER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (tAJREG-0161)

E - OPERATOR TRAINIfl0 + LICENSE EXAMINATION F - ADMINISTRATIVE 15) 0 - OPERATIONAL ERROR IEXPLAIN)

H - OTHERIEXPl'INI EXHIBIT I - SAME SOURCE I

.i PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8609 PHILADELPHIA. PA.19101 March 13, 1987 unsi e4t 4ooo j

Docket Nos. 50-277 50-278 Director Office of Inspection & Enforcement US Nuclear Regulatory Commission Washington, DC 20555 Attention:

Document Control Desk

SUBJECT:

Peach Bottom Atomic Power Station Monthly Operating Report Gentleman:

Attached are twelve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of February, 1987, forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Very truly yours, 7 -,

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W. M. Alden Engineer-In-Charge Licensing Section Nuclear Support Department Attachment cc:

Dr. T.

E. Murley, NRC Mr. T.

P. Johnson, Resident Inspector Mr. Stan P. Mangi, Dept. of Envir. Resources Mr. P. A. Ross, NRC (2 copies)

Mr. R. J. Clark, NRC Project Manager Mr. Thomas Magette, Maryland Power Plant Siting INPO Records Center

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