ML20211E218

Monthly Operating Repts for Jan 1987

ML20211E218
Person / Time
Site:	Peach Bottom
Issue date:	01/31/1987
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 8702240266
Download: ML20211E218 (14)

Text

~

Prach Bottom Atomic Power Station Narrative Summary of Operating Experience January, 1987 UNIT 2 Unit 2 operated at full power until January 10.

On January 10, load was reduced to approximately 620 MWe to 1

accommodate control rod pattern adjustment and condenser waterbox i

tube leak inspections.

Load recovery was completed on January 12.

Load was again reduced on January 16 to 680 MWe for control rod pattern adjustment and condenser waterbox tube leak inspections.

Full load was recovered on January 19.

On January 28, load was reduced to 75% power following a trip of the "A"

reactor feedpump turbine.

Unit 2 ended the report period operating at approximately 80% power with repairs to the "A"

reactor feedpump turbine coupling and overspeed trip mechanism in progress.

UNIT 3 Unit 3 began the report period starting up following a mini-outage for maintenance.

The turbine generator was placed on-line c

early on January 1.

On January 2, the reactor was manually shutdown to repair a steam leak on the

'D' main steam line inlet flange connection to the high pressure stage of the main turbine.

Startup commenced on i

January 6 following the completion of the flange repair, and the turbine-generator was synchronized to the grid on January 7.

[

Unit 3 operated at reduced loads (approximately 20-68%) from l

January 8 through January 13 due to persistent reactor water chemistry problems.

Condenser tube leaks were determined to be the cause.

Following condenser tube leak repairs, load was increased to 90% power where it was maintained to accommodate repairs to the 'G' and

'K' condensate filter demineralizer.

Unit 3 ended the report period operating at full load.

l l

kDj2 DOgK05000277 6 870131 R

PDR

\\/

[

Dockot No. 50-277 Attachm:nt to Monthly Operating Report for January, 1987 UNIT 2 REFUELING INFORMATION 1.

Name of facility:

Peach Bottom Unit 2 2.

Scheduled date for next refueling shutdown:

March 14, 1987 l

3.

Scheduled date for restart following refueling:

May 23, 1987 l

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.

i 5.

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

l l

Reload 7 license amendment submitted January 9, 1987.

6.

Important licensing considerations associated with refueling, l

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:

l (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:

l The spent ruel pool storage capacity has been relicensed for l

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.

- - _ - - - -.. - ~

Docket No. 50-277 Attachm:nt to Monthly Oparating Report for January, 1987 Page 2 UNIT 2 REFUELING INFORMATION (Continued) 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, 1998 (March 1995, with reserve full core discharge)

~

Docket No. 50-278 Attachmtnt to Monthly Operating Report for January, 1987 UNIT 3 REFUE NG INFORMATION 1.

Name of facility Peach Bottom Unit 3 2.

Scheduled date for next refueling shutdown:

September 12, 1987 3.

Scheduled date for restart following refueling:

June 17, 1988 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

4 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:

i 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

Docket No. 50-278 Atttchmant to Monthly Operating Report for January, 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 beers 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 is scheduled to begin on February 20, 1987 and should be completed in mid July, 1987.

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 core discharge) 10.

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

March, 1999 (March, 1996, with reserve full core discharge) l l

l l

l l

AVERAGE DAILY LMIT POIER LEVEL 00CKET NO. 50 - 177 LMIT PEACK COTTOM LMIT 2 DATE FEBRUARY 15.1967 CCIWANY PHILADELPHIA ELECTRIC CO W ANY L. L. MIDDLETON TECMGCAL ASSISTANT LICENSING SECTION 14JCLEAR SUPPORT DEPARDENT TELEPHOPE (215) 841-6374 MONTH JANUARY 1967 DAY AVERAGE DAILY PONER LEVEL DAY AVERAGE DAILY POMER LEVEL I P9E-+ET )

IptE-NET 3 1

1076 17 680 1

1 1072 18 467 3

1070 19 1057 0

1072 20 1074 5

1069 21 1078 6

1071 22 1074 7

1075 23 1076 0

1075 24 1075 i

I 9

1079 25 1075 10 711 26 1075 11 443 27 1077 12 1066 28 954 13 1075 29 846 j

1 10 1073 30 857 l

15 1075 31 857 l

16 1072

AVERAGE DAILY-LSIIT PCBE2 LEVEL DOCKET ND. 50 - 278 LMIT PEACH BOTTOM LMIT 3 DATE FEBRUARY 15,1987 CCWANY PHILADELPHIA ELECTRIC COWANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION DAJCLEAR SUPPORT DEPARTPENT TELEPHONE I2151 841-6374 MONTH JAMJARY 1987 DAY AVERAGE DAILY POMER LEVEL DAY AVERAGE DAILY POE R LEVEL 4 PME->ET 3 i PDE-tET1 1

344 17 963 2

383 18 968 3

0 19 988 4

0 20 1050 5

0 21 1056 6

0 22 1061 7

107 23 1069 8

425 24 1071 9

674 25 1070 1

I 10 677 26 1074 11 680 27 1074 12 775 28 1069 13 690 29 1071 l

14 889 30 1072 15 961 31 1072 15 970 l

L

OPERATING DATA REPORT DOCKET M3. 50 - 277 DATE FEBRUARY 15,1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION DAJCLEAR SUPPORT DEPARTNENT TELEPHOPE (2151841-6374 OPERATING STATUS

1. LMIT NAME PEACH BOTTOM LMIT 2 l NOTES LMIT 2 EXPERIENCED TMD l

l l

2. REPORTING PERIDDI JAPAJARY,1987 l

SCHEDULED LOAD REDUCTIONS l

l l

3. LICEldED THERMAL PONER(PMTis 3293 l

AND ONE FORCED LOAD l

l l

C. NAMEPLATE RATING IGROSS POE):

1152 l

REDUCTION.

l g

l

5. DESIGN ELECTRICAL RATING (PET P9Ela 1065 l

l g

6. MAXIPRM DEPENDABLE CAPACITY (GROSS PMEls 1098 l

l l

l l

7. MAXIPEM DEPENDA8LE CAPACITY INET PME):

1051 l

l C. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS lAJPSER 3 THROUGH 71 SINCE LAST REPORT, GIVE REASONSt

9. PONER LEVEL TO NHICH RESTRICTED, IF ANY INET PMEle

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YR-TO-DATE CLMJLATIVE

11. HOURS IN REPORTING PERIOD 744 744 110.256

12. IAJPSER OF HOURS REACTOR NAS CRITICAL 744.0 744.0 73,211.0

13. REACTOR RESERVE SHUTD0DM HOURS 0.0 0.0 0.0 1% HOURS GENERATOR ON-LINE 744.0 744.0 70,886.8

15. LMIT RESERVE SHUTD0004 HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (P91H) 2,508,656 2,308,656 210,140,025

17. GROSS ELECTRICAL ENERGY GENERATED (PMH) 771,510 771,510 69,142,510

13. NET ELECTRICAL ENERGY GENERATED (Ptet) 751,053 751,053 66,239,913 PAGE 1 0F 2

OPERATIM3 OATA REPORT (CONTIMJED)

DOCKET No. 50 - 277 DATE FEBRUARY 15,1987 THIS MONTH VR-TO-DATE CLARJLATIVE

19. UNIT SERVICE FACTOR 100.0 100.0 64.3

20. lA4IT AVAILABILITY FACTOR 100.0 100.0 64.3

21. lA4IT CAPACITY FACTOR (USING MDC ET) 96.0 96.0 57.2

22. LMIT CAPACITY FACTOR tuSING DER NET) 94.8 94.8 56.4

23. LA4IT FORCED OUTAGE RATE 0.0 0.0 13.5

24. SHUTDOP945 SCHEDULED OVER NEXT 6 MONTHS ITYPE, DATE, AM DURATION OF EACH)

REFUELING OUTAGE MARCH 14,1987 TO MAY 23,1987

15. IF SHUTD0bH AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP8

26. LMITS IN TEST STATUS (PRIOR TO COP 9tERCIAL OPERATIONil FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 COPHERCIAL OPERATION 07/05/74 PAGE 2 OF 2

~-

OPERATING DATA REPORT DOCKET ND. 50 - 278 DATE FEBRUARY 15 1987 COPW'LETED BY PHILADELPHIA ELECTRIC COMPANY L. L. NIDDLETON TECHNICAL ASSISTANT LICENSING SECTION 84JCLEAR SUPPORT DEPARTMNT TELEPHOE I215) 841-6374 OPERATING STATUS 1 tMIT NAME: PEACH SOTTOM LMIT 3 l NOTES: IMIT 3 EXPERIENCE TMO FORCED l l

l E. REPORTING PERIODI JAl4JARY,1987 l

CUTAGES.

l l

l

3. LICENSED THERMAL POMERiittT):

3293 l

l l

l C. NAMEPLATE RATING IGROSS 99E):

1152 l

l l

l

5. DESIGN ELECTRICAL RATING INET 99tE)8 1065 l

l l

l

6. NAXIttM DEPENDABLE CAPACITY IGROSS #9EIi 1098 l

l l

l

7. NAXIPEM DEPENDABLE CAPACITY INET 19 tele 1035 l

l C. IF CHANGES OCCUR IN CAPACITY RATINGS IITEMS 84JPSER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI

9. PONER LEVEL TO MHICH RESTRICTED, IF ANY INET 190Eli

10. REASONS FOR RESTRICTIONS. IF ANY8 THIS NONTH YR-TO-DATE CletJLATIVE

11. HOURS IN REPORTING PERICO 744 744 106:152 l

I

12. PA#sER OF HOURS REACTOR NAS CRITICAL 645.8 645.8 75,178.3 I

13. REACTOR RESERVE SHUTD0DN HOURS 0.0 0.0 0.0 1% HOURS SENERATOR ON-LINE 633.8 633.8 72,903.5

15. tMIT RESERVE SHUTD0DN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY SENERATED (PetHI 1,733.904 1.733.904 212.253.557 l

17. GROSS ELECTRICAL ENERGY GENERATED I994H) 575,480 575,480 69,631,352

18. NET ELECTRICAL ENERGY GENERATED Ip94H) 558.653 554.653 66,800,746 I

{

l PAGE 1 0F 2 l

OPERATING DATA REPORT (CONTIMJED)

DOCKET NO. 50 - 278 DATE FEBRUARY 15,1987 THIS NONTH YR-TO-DATE CLDRJLATIVE

19. LMIT SERVICE FACTOR 85.2 85.2 68.7

20. WIT AVAILABILITY FACTOR 85.2 85.2 68.7

21. WIT CAPACITY FACTOR tuSING NDC ET) 72.5 72.5 60.8

22. WIT CAPACITY FACTOR (USING DER ET) 70.5 70.5 59.1

23. LMIT FORCED OUTAGE RATE 14.8 14.8 8.3

24. SHUTDODNS SCHEDULED OVER NEXT 6 NONTHS ITYPE, DATE. AND DURATION OF EACH):

15. IF SHUTDOWN AT END OF REPORT PERIOD, ESTINATED DATE OF STARTUP8

26. LMITS IN TEST STATUS (PRIOR TO COPMERCIAL OPERATION)

FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 COPMERCIAL OPERATION 12/23/74 PAGE 2 0F t

WIT SHUTD0DedS AND POER REDUCTIONS DOCKET NO. 50 - 277 LMIT NAME PEACH BOTTOM WIT 2 DATE FEBRUARY 15,1967 REPORT MONTH JAWARY, 1967 Cow LETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION WCLEAR SUPPORT DEPARTENT TELEPHOE I2151841-H74 l

1 l

1 l METHOD OF l LICENSEE ISYSTEMICOMPONENTI CAUSE AND CORRECTIVE l

11YPElDURATIONlREASONISHUTTING D0Deel EVENT l CODE I CODE l ACTION TO

.1 DATE I (1)l IHOURS11 (2) l REACTOR E3) 1 REPORT S l (4) 1 ISI I PREVENT RECURRENCE I

I I

I I

I I

I I

) I C70110 l S l 000.0 1 H I 4

l WA l RB 1 CONROD l LOAD REDUCTION TO 60% FOR CONTROL ROD PATTERN 1

1 l

l l

l l

1 l ADJUSTMENT AND CONDENSER NATERBOX MAINTENANCE.

I 1

1 1

1 1

1 1

I 1

l CONROD l L AD REETION TO 60% M CO

) l C7011$ l S I 000.0 l H I 4

l WA l g l ADJUSTMENT AND CODGENSER MATERBOX MAINTENANCE.

l l

l l

l l

l I

I I

I i

l i

1 I

l 870128 l F l 000.0 i A l 4

l WA I CH I ECFLN l LOAD REDUCTION TO 78% DUE TO AN OVERSPEED TRIP J-l l

l l

l l

l l

l ON 2A FEED PLN.

I I

I ----- 1 I

I I

I I

l l l

1 1

I I

I I

I (1) til 13)

(4)

- FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS

- SCHEDULED A - EQUIPMENT FAILURE iEXPLAIN) 1 - MAWAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANL'AL SCRAM.

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

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER IEXPLAINI FILE (PAJREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE 15)

G - OPERATIONAL ERROR IEXPLAIN)

H - OTHERIEXPLAIN)

EXHIBIT I - SAME SOURCE

e I

LMIT SHUTD0ledS AfG POER REDUCTIONS DOCKET No. 50 - 278 LNIT NAM PEACH BOTTOM LMIT 3 DATE FEBRUARY 15 1987 REPORT PENTH JAMJARY,1987 COW LETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION MJCLEAR SUPPORT DEPARTMENT TELEPHONE I215) 841-6374 l

l l

l NETH00 0F l LICENSEE (SYSTEMICOWONENTI CAUSE AND CORRECTIVE 1

lTYPElDURATIONlk2ASONISHUTTING DODNl EVENT l CODE I CODE l ACTION TO I

1 1

1 I

I I

I I

4 l C70101 1 F 1 001.9 i H l 1

l N/A l HB l PIPEXX 1 MANUAL SHUTDODN FOR STEAM LEAK REPAIRS ON THE l

l 1

l l

l l

l l "C" MOISTURE SEPARATOR DRAIN TAE Male 4AY AND l

[

l l

l l

l l

l THE "D" INLET FLANGE COPMECTION TO THE HIGH l

l l

l l

l l

l l PRESSUE TURBINE. I12/28/861 1

I I

I I

I I

I i

1 l C70102 l F l 108.3 l H I 1

i N/A l HB l PIPEXX l MANUAL SHUTDODN FOR STEAM LEAK REPAIRS ON THE l

l l

1 l

l l

l l

"D" INLET FLANGE COPMECTION TO THE HIGH I

I I

I I

I I

I I PRESSURE TURBINE.

i l

1 ----- 1 I

I I

I I

i I

I i 110.2 I I

I I

I I

?

Ill it)

(3)

(4) f - FORCED REASON ETHOD EXHIBIT G - INSTRUCTIONS f-SCHEDULEDA - EQUIPMENT FAILURE IEXPLAIN)

1. MAPAJAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2. MANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE l

C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAINI FILE (MJREG-0161)

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

G - OPERATIONA?. ERROR IEXPLAIN)

H. OTHERtEXPLAINI EXHIBIT I - SAME SOURCE l

1

_ - _... -, _. _, _,,,.. _. _. _,. _.. _ -., _ _ - - ~. _,. -.., -..

PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 February 13, 1987 i

2isi 84i 4ooo Docket Nos. 50-277 50-278 1

Director

)

Office of Inspection & Enforcement 4

US Nuclear Regulatory Commission Washington, DC 20555 Attention:

Document Control Desk

SUBJECT:

Peach Bottom Atomic Power Station Monthly Operating Report Gentlemen:

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

Very truly yours,

/

i 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 l